Carolyn DeLane Heising Iowa State University

Industrial & Manufacturing Systems Engineering3017 Black Engineering Building

Ames, IA 50011 (515) 294-0124

http://www.imse.iastate.edu/heising.html cheising@iastate.edu

CURRENT POSITION

Professor of Industrial, Mechanical and Nuclear Engineering, Industrial & Manufacturing Systems Engineering, 1993

DEGREES

PhD, Mechanical Engineering, Stanford University, 1978

MS, Nuclear Engineering Science, Stanford University, 1975

BA, Applied Physics, University of California, San Diego, 1974

RESEARCH AREAS OF INTEREST Research Areas

Industrial & Manufacturing Systems Engr, Mechanical Engineering

Research Keywords

safety and reliability engineering continuous process improvement sustainable energy and nuclear power Modular Helium Reactor (MHR) LNG safety/Qatar gas engineering

Research Summary

Research areas include: reliability and quality engineering, probabilistic risk analysis, statistical quality control, total quality management, and technology safety assessment. In particular she is a well-known expert in nuclear power plant safety, condition monitoring, and predictive maintenance

PROFESSIONAL EXPERIENCE

Visiting Collaborator (Faculty Improvement Leave/Sabbatical), General Atomics Company, San Diego, California, 2008 - 2009

Acting Team Leader for Nuclear Power Analysis (Faculty Improvement Leave, Sabbatical), U.S. Department of Energy (DOE), Office of Nuclear Energy, Science and Technology, Department of Management, Planning and Analysis (NE-10), Washington, District of Columbia, 1999 - 2000

ASEE/DON Faculty Fellow, U.S. Department of Navy (DON), Naval Personnel Research and Development Center (NPRDC), San Diego, California, 1992

Visiting Professor, (sabbatical), Nuclear Engineering Department, University of Florida, Gainesville, Florida, 1990 - 1991

Professor (Tenured), Industrial Engineering and Information Systems Department, Northeastern University, Boston, Massachusetts, 1989 - 1993

Associate Professor, (tenured), Industrial Engineering and Information Systems Department, Northeastern University, Boston, Massachusetts, 1987 - 1989

USAF Faculty Fellow, Hanscom Field, Burlington, Massachusetts, 1985

Associate Professor, (untenured), Industrial Engineering and Information Systems Department, Northeastern University, Boston, Massachusetts, 1984 - 1987

Visiting Faculty, French Atomic Energy Commission, Valduc Nuclear Laboratory, Valduc, France, France, 1984

Visiting Faculty, Sandia National Laboratory, Albuquerque, New Mexico, 1981

Assistant Professor, (untenured), Nuclear Engineering Department, Massachusetts Institute of Technology (MIT), Cambridge, Massachusetts, 1980 - 1984

Program Engineer, Electric Power Research Institute, Palo Alto, California, 1978

Postdoctoral Research Associate, Nuclear Engineering Department, Massachusetts Institute of Technology (MIT), Cambridge, Massachusetts, 1978 - 1980

Systems Engineer, Brookhaven National Laboratory, Long Island, New York, 1976

Weapons Engineer, Lawrence Livermore Laboratory, Livermore, California, 1975

Graduate Research Assistant, Mechanical Engineering Department, Stanford University, Palo Alto, California, 1974 - 1978

Research Assistant, Physics Department, University of California, San Diego, San Diego, California, 1973 - 1974

CONSULTING

General Atomics, Consultant, San Diego, California, 2008 - 2009

Qatar University, Associate, Qatar University Gas Processing Center, Doha, Qatar, 2007 - present

U.S. Civilian Research and Development Foundation, Consultant, Washington, District of Columbia, 2000

Wisconsin Power and Light Company, Consultant, Madison, Wisconsin, 1997

Mid American Energy Corp., Consultant, Sioux City, Iowa, 1995

Virginia Electric Power Co., Consultant, North Anna, Virginia, 1992

Putnam, Bartlett and Hayes, Consultant, Boston, Massachusetts, 1989

World Bank, Consultant, Washington, District of Columbia, 1988

Kansai Electric Company, Consultant, Osaka, Japan, Japan, 1987

Florida Power and Light Company, Consultant, Juno Beach, Florida, 1987 - 1988

Boston Edison Company, Consultant, Boston, Massachusetts, 1985 - 1986

U.S Air Force (Brooks AFB), Consultant, San Antonio, Texas, 1984

Environmental Protection Agency, Consultant, Washington, District of Columbia, 1984

Oak Ridge National Laboratory, Consultant, Oak Ridge, Tennessee, 1982

Sandia National Laboratory, Consultant, Albuquerque, New Mexico, 1981

Pickard, Lowe and Garrick, Inc., Consultant, Newport Beach, California, 1981 - 1984

Clinch River Breeder Reactor Program, Oak Ridge National Laboratory, Consultant, Oak Ridge, Tennessee, 1981

Stone & Webster Corporation, Consultant, Boston, Massachusetts, 1981 - 1982

PROFESSIONAL DEVELOPMENT

Invited Speaker, World Nuclear Fuel Cycle Conference, Sydney, Australia, 2009

Invited Speaker, Department Colloquium, Nuclear Engineering Dept, UC Berkeley, 2009

Co-Chair, Co-Chair, Professional Development Committee, ANS June Meeting, Atlanta, Georgia, 2009

Visiting Collaborator, Global Nuclear Energy Partnership (GNEP) U.S. Department of Energy Contract to General Atomics Company, San Diego, California, 2008 - 2009

Committee Co-Chair, ANS National Winter Meeting, November, 2008, Co-Chair. Professional Development Committee, Reno, Nevada, 2008

Committee Co-chair, Co-Chair, ANS Professional Development Committee, ANS June Meeting, Anaheim, California, 2008

ISU ADVANCE Workshops, Facilitator/Organizer: 2005-2007; Attendee 2008, Iowa State University, 2005 - 2008

Department of Homeland Security Conference, Technologies for Critical Incident Preparedness, Attendee, San Diego, CA, 2005

Department of Homeland Security Conference, Working Together: R&D Partnerships in Homeland Security, Attendee, Boston, MA, 2005

ISU Women's Leadership Summit, Attendee, Iowa State University, 2005 - 2008

Society of Women Engineers National Conference, Attendee, Anaheim, CA, 2005

WEPAN/NAMEPA Joint National Conference, Attendee, Las Vegas, NV, 2005

4th Global Homeland Security Conference & Expo, Protecting the Nations Critical Infrastructure and Key Assets, Attendee, Washington DC, 2004

ANS Summer Meeting, Attendee, Pittsburgh, PA, 2004

American Nuclear Society Winter Meeting, Attendee, Washington, D.C., 2004

Amber Waves Homeland Security Tablestop Exercises, Iowa Homeland Security Department, Attendee, Des Moines, IA, 2004

International Conference on Advanced Technologies for Homeland Security, Attendee, University of Connecticut, School of Engineering, 2003

Iowa Food Security Conference, Attendee, Des Moines, IA, 2003

ISU Engineering College Academic Council Retreat, Attendee, Ames, IA, 2002

Affiliated Faculty Member, Ames Laboratory, Working with Dr. David Baldwin in the homeland security research area, Ames, Iowa, 2002 - 2007

12th International Conference on Women Engineers and Scientists, Attendee, Ottawa, Canada, 2002

Summit on Women in Engineering at the National Academy of Engineering, Attendee, Washington, D.C., 1999

Advisory Committee, ISU Women's Studies Program, Affiliated Faculty Member, Iowa State University, 1998 - 2008

American Power Conference, Attendee, Chicago, IL, 1998 - 2000

Women in Engineering Program Advocates Network (WEPAN) Conference, Attendee, Washington, D.C., 1997

Utility Working Conference of American Nuclear Society, Attendee, Amelia Island, FL, 1997 - 1999

National Institute of Industrial Engineers Research and National Conference, Attendee, Minneapolis, MN, May 1996; Miami, FL, May 1997; Banff, Alberta, Canada, May 1998; Phoenix, AZ, May 1999, 1996 - 1999

Project LEARN, Attendee, Ames, IA, 1996

ANS Executive Conference on Engineering Excellence, Engineering's Role in Providing Technically Excellent Products in a Cost-Efficient Manner, Attendee, Jupiter, FL, 1993

INTERNATIONAL EXPERIENCE

Invited Conference Speaker, Sydney Australia, World Nuclear Fuel Cycle Conference, 2009

Workshop Presenter, Doha, Qatar, Presented Workshop on LNG Safety for Qatar University LNG Research Center, 2008

Visiting Committee Member, Doha, Qatar, Qatar University Industrial Engineering Department (three IE faculty members from Texas A&M, Rutgers and ISU) in March, 2007

Associate, Doha, Qatar, Qatar University Gas Processing Center, 2007 - 2009

Representative, Ottawa, Canada, International Conference on Women Engineers and Scientists (ICWES '12) in July, 2002

National Institute of Industrial Engineers (IIE) Conference, Banff, Alberta, Canada, Presented technical refereed paper at Industrial Engineering Research Conference (IERC) at IIE conference in May, 1998

Speaker, Club Tremblant (near Montreal), Canada, Engineering Foundation Conference on "Creating New Paradigms for Developing and Retaining Women Engineers", 1998

Visiting Lecturer, South Africa, Delivered four invited lectures at South African engineering colleges (Capetown University, Pretoria University, Stellenbosch University and Rand Afrikaans University in Johannesburg) in February, 1997

Visiting Lecturer, Accra, Ghana, Lectured at NSF sponsored workshop on manufacturing for the African countries in Accra, Ghana during August 12-15, 1996

10th Pacific Basin Nuclear Conference, Kobe, Japan, International Steering Committee member for conference held October 20-25, 1996

Safety Culture in Nuclear Installations Conference sponsored by the International Atomic Energy Agency (IAEA), Vienna, Austria, Technical program committee member for ANS Austria/IAEA conference-- chaired technical session and presented technical paper during April 24-28, 1995

ANS liason to Slovenian Nuclear Society, Ljubljana, Slovenia, As member of the ANS International committee, was selected to be the liason to the Slovenian Nuclear Society and attended nuclear safety conference in Ljubljana in April, 1994

Invited Plenary Speaker, Lyon, France, Invited plenary speaker at European Nuclear Conference representing the American Nuclear Society in November, 1994

Nuclear Energy and Human Safety conference, Nizhni Novgorod, Russia, Technical Program Committee member for 4th annual scientific and technical conference of the International Nuclear Society, Moscow, 1993

American Nuclear Society (ANS) International Committee, La Grange Park, Illinois (ANS headquarters), Member, American Nuclear Society (ANS) International Committee supporting liasons with international nuclear societies such as the European, Japanese, Russian and Chinese nuclear societies, 1992 - 2000

Presentation at Hong Kong University of Science and Technology (HKUST), Hong Kong, China, Presentation at Hong Kong University of Science and Technology (HKUST) in Industrial Engineering department and visits to local industries in November, 1992

Invited Lecturer, Obninsk, Russia, Speaker at nuclear conference at Obninsk Atomic Research Center after Chernobyl in October, 1991

Consultant to Atomic Energy of Canada, Ltd (AECL), Toronto, Canada, Made invited presentation at AECL and consulted in January, 1987

Consultant to Kansai Electric Company, Osaka, Japan and Seoul, Korea, Presented lectures on safety engineering at Kansai Electric Company in Osaka Japan and then in Seoul Korea at the Korean Atomic Energy Research Institute (KAERI) in the summer, 1987

Delegate, ANS Safety Delegation, Former Soviet Union./Czech Republic/Hungary/East Germany, Presented lectures in the former Soviet Union on ANS safety delegation after the Chernobyl accident: Moscow, Kurchatov Institute, Kiev, Leningrad, Prague, Budapest, East Berlin in September, 1986

Delegate, ANS Safety Delegation, China, Month long delegation to China lecturing on safety with American Nuclear Society experts-- Beijing, Shanghai, Chengdu and Hong Kong in November, 1985

Invited Lecturer, Karlsruhe, Federal Republic of Germany, Presented talk on probabilistic risk assessment (PRA) at the 5th International Meeting on Thermal Reactor Safety sponsored by the European Nuclear Society (ENS), 1984

Visiting Faculty, Valduc (near Dijon), France, Summer research at French Atomic Energy Commission Valduc nuclear laboratory in July, 1984

Invited Lecturer, Kobe, Japan, Presented lecture on reactor accidents in Pressurized Water Reactors (PWRs) at Mitsubishi Electric Company Central Laboratory, 1981

Representative, Stockholm, Sweden, Attended the International Atomic Energy Agency (IAEA) conference on nuclear safety representing Prof. Norman C. Rasmussen of MIT Nuclear Engineering Department in October, 1980

Invited Guest Lecturer, Nykoping, Sweden, Presented talk at the Studsvik Nuclear Laboratory on the MIT Nuclear Safety/Reliability Program in October, 1980

UNDERGRADUATE ACTIVITIES

Minor in Nuclear Engineering, Coordinator, Member of proposal team for minor in nuclear engineering. Developing a web based course on nuclear safety for nuclear engineering consortium. This proposal is led by Profs. Greg Maxwell and Mike Pate in the Mechanical Engineering (ME) department., Fall 2007

Minor in Engineering Studies Program, Coordinator, Member of the minor in engineering studies (MES) coordinating committee. Also received support in the summer of 2006 to develop an MES course on sustainable energy and nuclear power., 2006, 2007

Undergraduate Nuclear Power Research at OPPD Ft Calhoun Station, Research Project, Royal Elmore was my undergraduate student involved in a funded research project from the Omaha Public Power District (OPPD) at the Ft Calhoun nuclear power plant. He initiated the proposal and carried out the research during the 2006-07 academic year., 1 Students, 2006

ME 431: "Sustainable Energy and Nuclear Power", Presenter, Fall 2006 course on nuclear power and sustainable energy., 15 Students, 2006

Engineering Diversity Course, Coordinator, Three year experimental course on diversity (IE 325x), entitled "Women and Men in the Engineering Workplace." This course had 20 students enrolled annually from the eight engineering college departments for a three year period (2003-2005). The co-coordinator of the course was Mary Goodwin in the college of engineering advising office., 60 Students, 2003, 2004, 2005

GRADUATE STUDENTS Major Professor

Dimitrios Karydas, PhD, , Northeastern University, Spring 1990

Andy Dykes, MIT, Nuclear Engineering Dept., PhD, , Spring 1984

Rafael Schechtman, MIT, Nuclear Engineering Dept, PhD, , MIT, Spring 1984

Hong-Nian Jow, PhD, , MIT, Spring 1984

Ching N. Guey, PhD, , MIT, Spring 1984

Martin G. Plys, PhD, , MIT, Spring 1984

Asif Khan, Iowa State, MS, Industrial Engineering, Spring 2009

Alexander Kleiman, Iowa State, MS, Systems Engineering, Spring 2008

Sathish C Sathyamurthy, Iowa State, MS, Industrial Engineering, Spring 2006

Karthikeyan Venkataraman, Iowa State, MS, Industrial Engineering, Spring 2006

Dattaprasad Kamat, Iowa State, MS, Industrial Engineering, Spring 2005

Aarthi Parthasarathy, Iowa State, MS, Industrial Engineering, Spring 2005

Gnanaguruparan Kandasamy, Iowa State, MS, Industrial Engineering, Summer 2005

H. Vepadharmalingam, Iowa State, MS, Industrial Engineering, Summer 2005

Girish Bhardwaj, Iowa State, MS, Industrial Engineering, Summer 2005

Ashok Guru, Iowa State, MS, Industrial Engineering, Summer 2005

Jothis K Kongu Ganapathi, Iowa State, MS, Industrial Engineering, Spring 2004

Bhavin Dhiren Mehta, Iowa State, MS, Industrial Engineering, Summer 2004

Shantha Esther Daniel, Iowa State, MS, Industrial Engineering, Spring 2003

Rahul Ratnakar Marathe, Iowa State, MS, Industrial Engineering, Spring 2003

Naveen Kekre, Iowa State, MS, Industrial Engineering, Spring 2003

Vinay Saraogi, Iowa State, MS, Industrial Engineering, Summer 2001

Mohammad Haj Yasin, Iowa State, MS, Industrial Engineering, Spring 2000

Raghu Krishnan, Iowa State, MS, Industrial Engineering, Spring 2000

Dharmarajan Subramanian, Iowa State, MS, Industrial Engineering, Fall 1999

Abhay Bhootra, Iowa State, MS, Industrial Engineering, Fall 1998

Ravi Prakash Konkimalla, Iowa State, MS, Industrial Engineering, Fall 1998

Anand Iyer Vaidyanathan, Iowa State, MS, Industrial Engineering, Fall 1997

Kimberley Lynn Mertz, Iowa State, MS, Industrial Engineering, Summer 1996

Patel Bimal Rohit, Iowa State, MS, , Spring 1996

Patricia Smith, Iowa State, MS, , Spring 1995

Sarat Agarwala, Iowa State, MS, , Spring 1995

Pravin Tampi, MS, , Spring 1995

Gregg Althens, Iowa State, MS, , Spring 1994

Michael Doherty, Northeastern University,Boston, MS, , Fall 1993

Ruth Evans, Northeastern University, Boston, MS, , Fall 1993

Robert Ware, Northeastern University, Boston, MS, , Fall 1993

Chih-Ko Chiu, Northeastern University,Boston, MS, , Fall 1993

Moto Sato, Northeastern University, Boston, MS, , Spring 1990

Guy Nicholas, Northeastern University, Boston, MS, , Spring 1990

Simon Melhem, Northeastern University, Boston, MS, , Spring 1989

William S. Grenzebach, Northeastern University, Boston, MS, , Spring 1988

Nicholas Shwayri, Northeastern University, Boston, MS, , Spring 1986

Dianne Luciani, Northeastern University, Boston, MS, , Spring 1986

Varghese P. George, MIT, Nuclear Engineering Dept, MS, , Spring 1985

Luca Otinetti, MIT, Nuclear Engineering Dept, M Tech, , Spring 1984

Cho Mak, MIT, Nuclear Engineering Dept, M Tech, , Spring 1984

Ari Raynsford, MIT, Nuclear Engineering Dept, M Tech, , Spring 1983

Harry J. Lipschitz, MIT, Nuclear Engineering Dept, MS, , Spring 1983

Hiroshi Noda, MIT, Nuclear Engineering Dept, MS, , Spring 1983

Meta Shaari Brown, MIT, Nuclear Engineering Dept, MS, , Spring 1983

James K. Liming, MIT, Nuclear Engineering Dept, MS, , Spring 1983

Virgilio Rodrigues Lopes de Oliveira, MIT, Nuclear Engineering Dept., MS, , Spring 1983

Andrew Dykes, MIT, Nuclear Engineering Dept, M Tech, , Spring 1982

Richard P.Burke, MIT, Nuclear Engineering Dept., MS, , Spring 1982

Earl Ike Patterson, MIT, Nuclear Engineering Dept, MS, , Spring 1982

Stephen C. Dinsmore, MIT, Nuclear Engineering Dept, MS, , Spring 1982

You-Hsin Yang, MIT, Nuclear Engineering Dept, MS, , Spring 1981

Cho Mak, MIT, Nuclear Engineering Dept., MS, , Spring 1981

Jose Lepervanche-Valencia, MIT, Nuclear Engineering Dept, M Tech, , Spring 1980

M. E. Byers, MIT, Nuclear Engineering Dept., MS, , Spring 1980

Isi Saragossi, MIT, Nuclear Engineering Dept, MS, , Spring 1980

Joseph R. Egen, MIT, Nuclear Engineering Dept, MS, , Spring 1979

Co-Major ProfessorCommittee Member

Douglas S McCorkle, Iowa State, PhD, Mechanical Engineering, Spring 2008

Stephanie D Loveland, Iowa State, PhD, Chemical Engineering, Spring 2008

Bo Xu, Iowa State, PhD, Industrial Engineering, Spring 2008

Muhammad Ali, Iowa State, PhD, Mechanical Engineering, Spring 2007

Mwafak Mohammed Shakoor, Iowa State, PhD, Mechanical Engineering, Spring 2006

Yong Jiang, Iowa State, PhD, Aerospace Engineering, Summer 2006

Wisam Abu-Jadayil, Iowa State, PhD, Mechanical Engineering, Fall 2005

Priya R Bhirud, Iowa State, MS, Systems Engineering, Fall 2005

Mayukh Ghosh, Iowa State, MS, Industrial Engineering, Summer 2005

Abhishek Saboo, Iowa State, MS, Industrial Engineering, Summer 2004

Charles Joseph Fazio, Iowa State, MS, Systems Engineering, Fall 2004

John Paul Barud, Iowa State, MS, Electrical Engineering, Spring 2001

RESIDENT INSTRUCTION

IE 537 Reliability and Safety Engineering Fall 2009 Iowa State UniversityI E 537 Reliability & Safety Engineering Fall 2007 I E 599A Creative Component: Industrial Engineering Spring 2007 I E 561 Continuous Quality Improvement of Process Spring 2007 M E 431 Nuclear Radiation Theory and Engineering Fall 2006 I E 599A Creative Component: Industrial Engineering Fall 2006 I E 599A Creative Component: Industrial Engineering Fall 2005 I E 599A Creative Component: Industrial Engineering Summer 2005I E 599A Creative Component: Industrial Engineering Spring 2005 I E 325X Women & Men in the Engineering Workplace Spring 2005 I E 537 Reliabilty & Safety Engineering Fall 2004 I E 599A Creative Component: Industrial Engineering Fall 2004 I E 599A Creative Component: Industrial Engineering Summer 2004I E 325X Women & Men in the Engineering Workplace Spring 2004 I E 599A Creative Component: Industrial Engineering Spring 2004 I E 561 Continuous Quality Improvement of Process Spring 2004 I E 537 Reliabilty & Safety Engineering Fall 2003 I E 599A Creative Component: Industrial Engineering Fall 2003 I E 325X Women & Men in the Engineering Workplace Spring 2003 I E 537 Reliability & Safety Engineering Fall 2002 I E 561 Continuous Quality Improvement of Process Spring 2002 I E 537 Reliability & Safety Engineering Fall 2001 I E 561 Continuous Quality Improvement of Process Spring 2001 I E 304 Engineering Economy Fall 2000 I E 561 Continuous Quality Improvement of Process Spring 1999 I E 436 Introduction to Reliability Engineering Spring 1999 I E 304 Engineering Economy Fall 1998 I E 461 Quality Engineering Fall 1998 I E 436 Introduction to Reliability Engineering Spring 1998 I E 461 Quality Engineering Fall 1997 I E 436 Introduction to Reliability Engineering Spring 1997 I E 561 Continuous Quality Improvement of Process Spring 1997 I E 461 Quality Engineering Fall 1996 I E 436 Introduction to Reliability Engineering Spring 1996 I E 304 Engineering Economy Spring 1996 I E 304 Engineering Economy Fall 1995

I E 461 Quality Engineering Fall 1995 I E 304 Engineering Economy Spring 1995 I E 461 Quality Engineering Fall 1994 I E 436 Introduction to Reliability Engineering Spring 1994 I E 561 Continuous Quality Improvement of Process Spring 1994

NON-RESIDENT INSTRUCTION

Safety Engineering in the LNG Industry workshop, January 14-15,2008, Qatar University Gas Processing Center, Doha, Qatar, 2008

Midwest Nuclear Science and Engineering Consortium Symposium at University of Missouri, Columbia, 2005

ANS Utility Working Conference Amelia Island Florida Workshop on Continuous Process Improvement, 2003

Nuclear Industry Security Professional Development Workshop at ANS International Meeting, New Orleans, 2003

ANS Utility Working Conference Amelia Island Florida Workshop on Continuous Process Improvement, 2002

ANS Utility Working Conference Amelia Island Florida Workshop on Preventive Maintenance and Condition Monitoring, 1999

ANS Utility Working Conference Amelia Island Florida Workshop on Preventive Maintenance and Condition Monitoring, 1998

Safety and Quality Culture: Methods for Continuous Process Improvement at ANS National Meeting, San Francisco, 1995

POST DOCTORAL AND VISITING SCIENTIST

Dr Eric Steinfelds, University of Florida, Gainesville, 2003

RESEARCH PROJECTS

Design Studies for MHR to Support DOE Projects: GNEP, NGNP, Deep Burn (DB)-MHR

A Multi State, Multi-University Collaborative Approach in Developing Innovative Educational Modules to Enhance and Expand Nuclear Education Infrastructure - The Big 12 Engineering Consortium will collaboratively develop high quality lessons and 1-3 credit modules to be offered in a distance education format to students at Big 12 schools and other constituencies. Topics covered include: intro to nuclear engineering, the nature of radiation, Gen III and IV reactor concepts, economics of nuclear power, human factors, nondestructive evaluation, materials for reactor applications, probabilistic risk assessment, nuclear plant safety, and security, etc.

A Study of Reprocessing and Breeder Cost-Benefits - Thirty thousand dollars. Mechanical Engineering Department, Stanford University. Sponsor: Electric Power Research Institute (EPRI), Prof. Thomas Connolly, Major Professor, Principal Investigator: C. D. Heising. 1977-78. Funded doctoral thesis work.

A Comparative Assessment of the LMFBR and Advanced Converter Fuel Cycles with Quantification of the Relative Diversion Resistance - Fifty thousand dollars; MIT:

Nuclear Engineering Department, Sponsor: Electric Power Research Institute (EPRI), Nuclear Power Division, R. F. Williams, Project Manager. Co-principal investigator with MIT Professor and Chair, Nuclear Engineering Department, Dr. Norman C. Rasmussen, 1978-80.

Analyzing the Safety Impact of Containment Inerting at Vermont Yankee - Twenty five thousand dollars. 1980-81. MIT Nuclear Engineering Department. Sponsor: Yankee Atomic Electric Company. Principal Investigator. Project Managers: J. Turnage and E. Pilat.

Generic Nuclear Safety Issues: Methods of Analysis - Sixty thousand dollars. January 1980-81. MIT Nuclear Engineering department. Sponsor: Nuclear Safety Analysis Center. Principal Investigator. E. Zebroski and R Breen, Project Managers.

Methods for Establishing Real Time Considerations in Emergency Planning for Reactor Accidents - Fifty thousand five hundred thirteen dollars. MIT Nuclear Engineering Dept. 1981-82. Sponsor: Sandia National Laboratory. Principal Investigator. D. C. Aldrich, Project Manager.

Common Cause Analysis: A Review and Extension of Existing Methods - Sixty thousand dollars. MIT Nuclear Engineering Dept. Sponsor: MIT Utility Group. Co-principal investigator with Prof. Norman C. Rasmussen. R. Bagley and S. Bardhan, project managers.

Development and Application of the MARCH Code - One hundred thousand dollars.MIT Nuclear Engineering dept. August 1981-82. Co-principal investigator: Prof. Mujid Kazimi, PI. Sponsor: Electric Power Research Institute (EPRI).

Core-Concrete Interaction Models and Experiments: Impact on Containment Pressure History in Severe Reactor Accidents - Fifty thousand dollars. Sept. 1982-83. MIT Nuclear Engineering Dept. Sponsor: Fauske Associates. Principal Investigator. Project Manager: R. Henry.

Uncertainty Analysis in Risk Studies of High Level Waste Repositories - Eighty three thousand five hundred and nine dollars. MIT Nuclear Engineering Department. February 1982-83. Principal Investigator. Sponsor: Sandia National Laboratory. N. Ortiz, project manager.

Common Cause Analysis Methods for Large-Scale Utility PRAs - Sixty eight thousand dollars. January 1983-84. MIT Nuclear Engineering Department. Principal Investigator. Sponsor: MIT Utility Working Group, Northeast Utilities. R. Bagley and B J Garrick, Project Managers.

Bayesian Methods for Assessing USAF System Performance - Twenty five thousand dollars. Summer 1985. USAF-UES summer research program for visiting faculty and students, Hanscom AFB, Boston, Massachusetts. Principal Investigator.

Data Analysis of Fossil Fuel Power Plant Components for Life Extension and Improved Availability - Forty six thousand four hundred dollars. April 1986-87. Northeastern University, Industrial Engineering Dept. Principal Investigator. Sponsor: Boston Edison Company. R. Zimbone, project manager.

Methods for the Computerized Control of Nuclear Power Plants for Improved Safety, Quality and Productivity - Two hundred fifty one thousand dollars. September 1986-

January 1989. Northeastern University, Industrial Engineering Department. Principal Investigator. Sponsor: U.S. Department of Energy (DOE).

Intelligent Risk Assessment/simulation Model - Sixty thousand dollars.1989-92, Northeastern University, Industrial Engineering department. Co-principal investigator with Profs. Jason Kim and M. Silevitch. Sponsor: Office of the Secretary of Defense, Washington, DC.

System Analysis for Process Improvement - Fifteen thousand dollars.Summer 1992. U. S. Department of the Navy (DoN)/ASEE Program for Visiting Faculty. Naval Personnel Research Development Center (NPRDC). San Diego, California.

Design of Condition Monitor for Nuclear Power Plants Based on Statistical Quality Control - Four thousand dollars.ISU Industrial Engineering Dept. January 1994. College of Engineering seed money grant. Principal Investigator.

Fault Identification by Network Recognition of CUSUM Chart Patterns - Sixteen thousand four hundred dollars. September 1994-95. ISU Electric Power Research Center Affiliate Program. Principal Investigator.

Improving Power Plant Availability Through Statistical Process Control - Fifteen thousand dollars. May 1995-96. ISU Electric Power Research Center (EPRC). Principal Investigator. MidAmerican Energy Co. sponsor.

A Web Based Process Monitoring System at Ft Calhoun Nuclear Power Plant - Twenty thousand dollars. August 1998-August 1999. Sponsor: Omaha Public Power District ) through ISU Electric Power Research Center (EPRC).

Supporting the Columbia Plant Process Control Effort on Tube Leaks and Boiler Fouling - Twenty thousand dollrs. ISU Electric Power Research Center (EPRC). Sponsor: Alliant Energy Company. Principal Investigator.

A Multiple Regression Model for the Columbia Power Plant - Forty thousand dollars. August 1999-2001. Sponsor: Alliant Energy Corporation, Electric Power Research Center, (EPRC), Iowa State University (ISU).

Online Condition Monitoring Using a Web Based Process Monitoring System Using Neural Networks/Virtual Reality Model of the Ft Calhoun Reactor Coolant Pumps - Forty thousand dollars. August 1999-May 2001. ISU Electric Power Research Center (EPRC). Sponsor: Alliant Energy Corporation.

Nuclear Power Plant Analyses - Sixty six thousand six hundred twelve dollars. August 1, 1999- July 31, 2000. Sponsor: U. S. Department of Energy (DOE), Office of Nuclear Energy (NE), Washington, DC. (IPA assignment; faculty improvement sabbatical leave).

Applying Statistical Analyses to Control the Power Output at Columbia Power Plant - Two thousand two hundred forty two dollars. June, 2001- August 2001. Sponsor: Alliant Energy Corporation through ISU Electric Power Research Center (EPRC).

Advance Institutional Transformation Award: Comprehensive Institutional Transformation - Three million three hundred sixty thousand dollars for five years; September 2006-2011. Co-principal investigator for first year (9/06-7/07). Member of proposal writing team from 2002-2007. Sponsor: National Science Foundation (NSF) ADVANCE program, Washington, DC.

Life Cycle Management (LCM) Analyses Applications - .Thirty thousand dollars. July 1, 2001--June 30, 2002. ISU , IMSE Dept. Sponsor: Omaha Public Power District (OPPD). Principal Investigator.

Life Cycle Management (LCM) Analyses Applications to the Ft. Calhoun Nuclear Power Plant: Maintenance and Aging Management Study of Critical Components - Fifteen thousand dollars. July 1, 2002- June 30, 2003. ISU IMSE Dept., Sponsor: Omaha Public Power District (OPPD). Principal Investigator.

Replacement Chemicals for pH Neutralization in PWR Reactor Coolant System - Fifteen thousand dollars. January 2006- January 2007. ISU IMSE Dept. Sponsor: Omaha Public Power District (OPPD). Principal Investigator.

EXTENSION / PROFESSIONAL PRACTICE Professional Practice

Society of Women Engineers, Chair, Women in Academia Committee, national Society of Women Engineers (SWE), 2006 - 2008

American Nuclear Society, Vice Chair, American Nuclear Society (ANS) Professional Development Coordination Committee, 2004 - 2010

American Nuclear Society, Chair, American Nuclear Society (ANS) Planning Committee, 2003 - 2007

American Nuclear Society, Member, Professional Women In ANS Committee, 2001 - 2010

American Nuclear Society, Chair, Professional Women in ANS, 1998 - 2001

Institute of Industrial Engineers, Senior Member, Institute of Industrial Engineers (IIE), 1990 - 2011

Extension

Iowans for Hillary, Member, Steering Committee, Story County Campaign for Hillary Rodham Clinton, 2007

Florida Power & Light/Duane Arnold Energy Center, Visit to Duane Arnold Energy Center (DAEC) with Dr. Gary Mirka, chair, IMSE department for industrial outreach/extension, September 17, 2007

Des Moines Lions Club, Spoke at Des Moines Lions Club as member of ISU Speaker's Bureau on topic of nuclear power Sept 13, 2007

Ames Women's Club, As speaker in ISU Speaker's bureau, invited to talk on nuclear power at Ames Women's Club, 2006

Des Moines Register, Five op-ed (editorial) pieces on nuclear power and the environment, 2006 - 2009

ISU Program for Women in Science and Engineering (PWSE), Taking the Road Less Travelled "Becoming an IE, ME or NE". ISU PWSE program recruits girls from across Iowa from 6th-12th grades into engineering and science fields, 1993 - 2005

PROFESSIONAL SOCIETIES AND ORGANIZATIONS Leadership

Society of Women Engineers (SWE) national meeting in Nashville, Tennessee, October 24-27, 2007 presented professional development session on "Success Secrets in Academe"; also invited Dean Mark Kushner to present on Faculty Leadership Roles in 2050., Committee Chair, 2007

American Nuclear Society, June 2007 meeting, Boston, MA, Committee Chair, 2007

National American Nuclear Society Invited Panel on "Diversity in the Nuclear Industry", Albuquerque, New Mexico, Panel Member, 2006

Chaired panels on "Success Stories in Academe" and "Academic Leadership", SWE national conference, October, 2006, Kansas City with Dean Mark Kushner panelist and presenter., Session Chair, 2006

American Nuclear Society national meetings, June and November 2006, Reno and Albuquerque as planning committee chair, Committee Chair, 2006

National Science Foundation ADVANCE Program Principal Investigators Meetings, Arlington, VA at NSF headquarters representing ISU ADVANCE program 2006,2007, Representative, 2006 - 2007

Co-organizer of session, "How to Obtain Tenure", SWE Conference, Kansas City, Organizer, 2006

Society of Women Engineers National Committee on Women in Academia, Chair, 2006 - 2008

American Nuclear Society national meetings June and November 2005, San Diego and Washington, DC as planning committee chair, Chair, 2005

National Planning Committee, American Nuclear Society, Chair, 2004 - 2007

American Nuclear Society (Organized and presented at the annual winter meeting of the American Nuclear Society (ANS) November 2003), Coordinator, 2003

American Nuclear Society (Organized and presented at the annual American Nuclear Society (ANS) Utility Working Conference in Amelia Island, Florida, August 2003 workshop on lifecycle management of nuclear plants based on OPPD funded research., Coordinator, 2003

American Nuclear Society (Organized and offered workshop on Life Extension and Life Cycle Management (LCM), ANS Utility Working Conference), Coordinator, 2002 - 2003

Professional Women in ANS Committee (PWANS), Chair, 1998 - 1999

American Nuclear Society (ANS) Professional Development Coordination Committee (PDCC), Chair, 1998 - 2008

Board Liaison to Kansas, Missouri and Nebraska Local Sections, American Nuclear Society, Liaison, 1997 - 1998

Board Liaison to Nuclear Operations Division, American Nuclear Society, Liaison, 1997 - 1998

American Nuclear Society (Technical Program Chair, ANS University Working Conference, Nuclear Engineering Education), Chair, 1995

American Nuclear Society (Organized and offered a professional development shortcourse, entitled: "Safety and Quality Culture"), Coordinator, 1995

Technical Program Chair, First ANS University Working Conference, Philadelphia, Pennsylvania, June 23-24, 1995., Chair, 1995

Northeastern Section, American Nuclear Society, Chair, 1982 - 1983

Membership

Technical Program Committee Member for Fifth-Eleventh ANS Utility Working Conferences, Amelia Island, Florida, August 1998-2004., 1998 - present

Technical Program Committee Member, Third ANS University Working Conference, Orlando, Florida, May 31, 1997., 1997 - present

Technical Program Committee Member, Second ANS University Working Conference, Reno, Nevada, June 14-15, 1996, 1996 - present

International Steering Committee, 10th Pacific Basin Nuclear Conference, Kobe, Japan, October 20-25, 1996., 1996 - present

Technical Program Committee, ANS Austria Local Section Conference, Safety Culture in Nuclear Installations, Vienna, Austria, 1995 - present

Technical Program Committee, ANS Second Workshop on Safety of Soviet Plants, Washington D.C., November 1994., 1994 - present

Technical Program Committee Member, ANS PRA Topical Meeting, January 1993, Clearwater Beach, Florida;, 1993 - present

Board Liaison Member for Scholarship Policy and Coordination, American Nuclear Society, 1992 - present

Professional Women in ANS Committee, American Nuclear Society, 1989 - present

NRSD Program Committee, American Nuclear Society, 1982 - present

Education Division Executive Committee, American Nuclear Society (ANS), 1982 - present

Tau Beta Pi (Inducted Massachusetts Beta Section (MIT)), 1982 - present

Institute of Industrial Engineers, 1982 - present

Organizing Committee, 4th Annual Scientific and Technical Conference of the International Nuclear Society, Moscow

Program Committee, 2009 American Nuclear Society Risk Management Meeting, 2008 - 2009

San Diego Section, American Nuclear Society, 1994 - 2007

National Board of Directors, American Nuclear Society (ANS), 1992 - 1998

International Committee, American Nuclear Society (ANS), 1992 - 1995

NEED Committee, American Nuclear Society, 1989 - 1992

Honors and Awards Committee, American Nuclear Society (ANS), 1988 - 1990

Board Member, Northeastern Section, American Nuclear Society (ANS), 1982 - 1993

Society of Women Engineers, 1982 - 2007

INSTITUTIONAL SERVICE

Iowa State University

ISU Speakers Bureau, Presenter, 2006 - 2008, Presented talks on nuclear power and energy policy at Iowa based citizens groups (Kiwanis, Ames Womans Club, etc). Was one of the top presenters as denoted by Provost Hoffman at the speakers bureau luncheon (5/1/08)

Faculty Senate Resource Policy Allocations (RPA) Committee advising Provost Hoffman, Member, 2006 - 2007

Faculty Senate Spring Conference Organizing Committee, Member, 2005 - 2007

Faculty Senate Committee on Women and Minorities, Chair, 2004 - 2007, Worked on issues of recruitment and retention of women and minority faculty members.

UCW Subcommittee on the Status of Women in the College of Engineering, Chair, 2003 - 2004

Faculty Budget Advisory Committee to Provost Ben Allen, Member, 2003

NSF ADVANCE team, Member, 2002 - 2007

Faculty Senate Committee on Committees (as engineering college caucus chair), Member, 2001 - 2007

Faculty Senate, Member, 2001 - 2007

Executive Board, Faculty Senate, Member, 2001 - 2007

Faculty Senate Liaison, University Committee on Women (UCW), Member, 2001 - 2007

UCW Subcommittee on the Status of Women in the College of Engineering, Member, 2001 - 2004

ISU Women' s Studies Program, Member, 2000 - 2007, Affiliated Faculty Member

Advisory Committee on Women's Studies Program, Member, 1998 - 2007

University Committee of Women Full Professors, Member, 1995 - 1997, Co-Convenor (with Prof. Mary Huba, Education College (1995-97))

Search Committee for Engineering Dean (1994-97), Member, 1994 - 1997

University Committee on Women, Member, 1994 - 1997

College

Professional Development Committee, Member, 2009 - 2011

Engineering College Promotion and Tenure Committee, Member, 2001 - 2008

Engineering College Academic Council, Member, 2001 - 2007

Engineering Caucus of the Faculty Senate, Chair, 2001 - 2007

College Professional Development Committee, Member, 1995 - 1998

International Program Task Group, Member, 1994 - 1995

Dean' s Ad-Hoc Committee on Women Faculty in Engineering, Member, 1993 - 1998

Department

Recruiting and Retention Committee, Member, 2001 - present

Honors and Awards Committee, Member, 2001 - present

Faculty Search Committee, Member, 1998 - 1999

Undergraduate & Graduate Seminars in IMSE Department, Member, 1997 - 1998

Alumni Relations, Member, 1996 - 1997

Honors and Awards, Member, 1993 - 1997

Promotion and Tenure, Member, 1993 - 1994

Committee on Spring Banquet Review, Member, 1993 - 1994

Committee H; ABET Review, Member, 1993 - 1994

HONORS AND AWARDS

ISU Shared Leadership for Institutional Change (SLIC) Program, Iowa State University, 2003

Young Scholar Award, American Association of University Women (AAUW), 1987

National Science Foundation George Washington University Special Seminar Award, George Washington University, 1980

Best Student Paper, Institute of Nuclear Materials Management, 1978

FUTURE PLANS

Faculty Improvement Leave/Sabbatical at General Atomics Company in San Diego to work on Global Nuclear Energy Partnership program of U.S. Department of Energy (DOE), 2008 - 2009

EVENTS

Technical Program Committee, 2009 ANS Risk Management Meeting, November, Washington, DC, Member, 2009

Department Colloquium, UC Berkeley Nuclear Engineering Department, "Safeguards Considerations of Thorium Utilization in Nuclear Reactor Fuel Cycles", Presenter, 2009

74th GT-MHR Working Group Meeting, MHR-Energy Group General Atomics hosting meeting of Russian Federation organizations meeting on the GT-MHR prototype being build at the Kurchatov Institute, Moscow, Russia, Attendee, 2008

Workshop on Nuclear Proliferation, Workshop on Nuclear Proliferation sponsored by DOE, University Missouri, July 2005., Presenter, 2005

Amber Waves Homeland Security Tablestop Exercises, Iowa HomelandSecurity Department, Des Moines, IA, May- October, 2004. (with Dr. David Baldwin, Ames Lab), Attendee, 2004

ANS Board Meeting and Strategic Planning Meeting, ANS Board Meeting and Strategic Planning Meeting, March 1999, Washington, D.C., Committee Chair, 1999

ANS Board Directors retreat, ANS Board of Directors retreat, August 23-26, 1997 and October 15-18, 1997, Lisle, Illinois., Board Member, 1997

ANS Utility Working Conference, Technical Program Committee Member, ANS Utility Working Conference on Meeting the Challenge of Cost-Effectiveness, Amelia Island Plantation, Amelia Island, Florida, August 20, 1997., Committee Member, 1997

GRANTS/CONTRACTS/GIFTS

Life Cycle Management (LCM) Analyses Applications to the Ft. Calhoun Nuclear Power Plant, OPPD and Ft. Calhoun Nuclear Power Plant (2001-07-01)

Predictive Maintenance and On-Line Condition Monitoring, ISU Electric Power Research Center Power Affiliate Program (1996-05-01)

Life Cycle Management (LCM) Analyses Applications to the Ft. Calhoun Nuclear Power Plant: Maintenance and Aging Management Study of Critical Components, Ft. Calhoun Nuclear Power Plant (2002-07-01)

Applying Statistical Analyses to Control the Power Output at Columbia Power Plant, Alliant Energy Corporation (2001-06-01)

Improving Power Plant Availability through Statistical Process Control, ISU Electric Power Research Center, MidAmerican Energy (1995-05-01)

Online Condition Monitoring Using a Web Based Process Monitoring System Using Neural Networks/Virtual Reality Model of the Ft. Calhoun Reactor Coolant Pumps, ISU Electric Power Research Center, OPPD-Ft. Calhoun Nuclear Power Plant (1999-08-01)

Fault Identification by Network Recognition of CUSUM Chart Pattern, ISU Electric Power Research Center Affiliate Program (1994-09-01)

A Multiple Regression Model for the Columbia Power Plant, ISU Electric Power Research Center, Alliant Energy Corporation (1999-08-01)

Design of Condition Monitor for Nuclear Power Plants Based on Statistical Quality Control, College of Engineering Grant (2004-01-01)

Supporting the Columbia Plant Process Control Effort on Tube Leaks and Boiler Fouling, ISU Electric Power Research Center, Alliant Energy Corporation (1998-08-01)

Ph Neutralization in PWR Reactors, OPPD (2006-02-01)

A Web Based Process Monitoring System at Ft. Calhoun Nuclear Power Plant, ISU Electric Power Research Center, OPPD (1998-08-01)

Improving Power Plant Availability Through Statistical Process Control at Rock River Generating Station, ISU Electric Power Research Center (1997-08-01)

Predictive Maintenance and On-Line Condition Monitoring at the Neal South Fossil Plant, ISU Electric Power Research Center, MidAmerican Energy (1996-08-01)

Advance at Iowa State University: Comprehensive Institutional Intervention Strategy, National Science Foundation (2006-10-01)

PUBLICATIONS Journal Articles: Refereed

1. Heising, C.D.. 2009. Safeguards Considerations of Thorium Utilization in Nuclear Reactor Fuel Cycles. Science and Technology of Nuclear Installations, Submitted.

2. Heising, C. D., and A. Rangarajan. November, 2001. A statistical analysis to predict the power output for alliant energy. International Journal of Industrial Engineering.

3. Heising, C. D., and B. Patel. February 1997. Statistical analysis of the Ft Calhoun reactor coolant pump system. Annals of Nuclear Energy, 24(3), 156-167.

4. Heising, C. D., and J. A. Zamora-Reyes. May 1996. On a bayesian estimation procedure for determining the average ore grade of an uranium deposit. Annals of Nuclear Energy, 23(7), 543-552.

5. Schechtman, R., and C. D. Heising. June, 1996. Risk assessment of the beneficial impact of a filtered venting containment system in a PWR with large, dry containment. Annals of Nuclear Energy, 23(8), 641-661.

6. Heising, C. D., and V. L. Oliveira. February, 1995. A unified approach for calculating the core melt frequency due to internal and external initiating events. Risk Analysis, 15(1).

7. Heising, C. D., and W. S. Grenzebach. December 1994. A computerized diagnostic system for nuclear power plant control rooms based on statistical quality control. Nuclear Technology, 108(3), 421-443.

8. Grenzebach, W. S., C. D. Heising, and T. J. Marx. December 1994. Statistical analysis of reactor coolant pump data for improved operations. Nuclear Technology, 108(3), 421-433.

9. Heising, C. D., and W. S. Grenzebach. 1989. The ocean ranger oil rig disaster: a risk analysis. Risk Analysis, 9(1), 55-62.

10. Heising, C. D. 1987. Risk assessment: controlling hazardous materials. Journal of Hazardous Materials, 15, 123-135.

11. Heising, C. D., and D. M. Luciani. 1987. Application of computerized methodology for performing common cause failure analysis: the MOCUS-BACFIRE beta factor (MOBB) code. Reliability Engineering, 17, 193-210.

12. Heising, C. D., and N. Shwayri. 1987. An application of the two-stage bayesian method to estimate the outage rate of oil-fired boilers. Reliability Engineering, 18, 22-23.

13. Heising, C. D., and V. George. February 1986. Nuclear financial risk: economy-wide costs of a reactor accident. Energy Policy, 45-52.

14. Guey, C. N., and C. D. Heising. 1986. Development of common cause failure analysis method: the inverse stress-strain interference (ISSI) technique. Stuctural Safety, 4, 63-67.

15. Laviron, A., and C. D. Heising. 1985. Error transmission in large, complex fault trees using the ESCAF method. Reliability Engineering, 1, 181-192.

16. Heising, C. D., and E. I. Patterson. 1984. Plant specification of human error through a two-stage bayesian procedure. Reliability Engineering, 7, 21-52.

17. Gierszewski, P., and C. D. Heising. January 1984. A reliability analysis of the emergency power system of the starfire TOKOMAK. Nuclear Technology: Fusion, 5, 42-54.

18. Burke, R. P., C. D. Heising, and D. C. Aldrich. 1984. In plant methods for calculating systems unavailability due to common cause failure. Reliability Engineering, 8, 101-116.

19. Heising, C. D., and A. Mosleh. July 1983. A bayesian estimation of core damage frequency incorporating historical data on precursor events. Nuclear Safety, 24(4), 485-493.

20. Heising, C. D. 1983. Development of unavailability expressions for one and two components with periodic testing and common cause failures. Reliability Engineering, 6, 229-254.

21. Heising, C. D., and S. Dinsmore. 1982. A method for quantifying the reliability of instrumentation for engineering safety features to improve accident sequence recognition in reactor control rooms. Nuclear Engineering and Design, 74, 287-292.

22. Heising, C. D. June 1982. Quantifying nuclear fuel cycle diversion resistance. Energy Policy, 10(2), 101-108.

23. Heising, C. D. 1982. The determination of plant status during abnormal reactor operating conditions: accident sequence identification. Nuclear Engineering and Design, 74, 137-148.

24. Heising, C. D. 1981. Small power reactors for electricity generation in the developing world. Applied Energy, 8, 19-49.

25. Heising, C. D., and J. Lepervanche-Valencia. 1981. An evaluation of accident hydrogen control in boiling water reactors. Nuclear Engineering and Design, 64, 319-329.

26. Heising, C. D. 1981. A survey of methodology for the global minimization of concave functions subject to convex constraints. OMEGA: The International Journal of Management Science, 9(3), 313-319.

27. Heising, C. D. October, 1980. An evaluation of the plutonium denaturing concept as an effective safeguards method. Nuclear Technology, 50(3), 242-252.

28. Heising, C. D., I. Saragossi, and P. Sharafi. November 1980. A comparative assessment of the economics and proliferation resistance of advanced nuclear energy systems. Energy, 5(11), 1131-1155.

Bulletins, Reports, or Conference Proceedings

29. Barsell, A., C. D. Heising, K. Fleming, S. Kaplan, and B. J. Garrick. 1982 Indian point risk assessment. In . March 1982.

Bulletins, Reports, or Conference Proceedings: Refereed

30. Heising, C.D.,Bozek, A., and Shenoy, A.. 2009 GNEP Deployment Studies: A Path Forward. In GA Project 30293. January, 2009, General Atomics Company, San Diego, California, In Press.

31. Heising, C.D.. 2009 Fuel Cycle Safeguards Considerations Including Thorium. In GA Project 30293. April 2009, General Atomics Company, San Diego, California, Accepted.

32. Heising, C.D.. 2009 Comments on the GNEP Draft Programmatic Environmental Impact Statement (PEIS). In GA Internal Project A04962. May 2009, General Atomics Company, San Diego, California, Accepted.

33. Heising, C.D.. 2009 "Closing the Nuclear Fuel Cycle: Thorium and Advanced Alternatives". In Proceedings of the World Nuclear Fuel Cycle Conference, Sydney, Australia, April 21-24, 2009. April, 2009, World Nuclear Association, Accepted.

34. Heising, C.D.. 2009 Safeguards Considerations of Thorium Utilization in Nuclear Reactor Fuel Cycles. In Proceedings of the American Nuclear Society (ANS) Risk Management Embedded Topical Meeting, Washington, DC. November 15-19, 2009.. 2009, American Nuclear Society, Accepted.

35. Heising, C. D., and A. Kleiman. 2008 Systems approach to process improvement model for post-LOCA water management at the ft calhoun nuclear power plant. In Proceedings of the 9th Cairo University International Conference on Mechanical Design and Production (MDP-9), Cairo, Egypt, January 7-9, 2008, Cairo University, In Press.

36. Heising, C. D., and E. Steinfelds. 2006 Secure energy infrastructures: power plants and research reactors. In Institute of Industrial Engineers (IIE) Annual Conference, Orlando, Florida. May 2006, Institute of Industrial Engineers (IIE).

37. Heising, C. D., and E. Steinfelds. 2006 Secure energy infrastructures: nuclear power plant security. In 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad, New Mexico. April 2006, American Nuclear Society (ANS).

38. Heising, C. D., and E. Steinfelds. 2005 Secure energy infrastructures: nuclear power plant security. In Proceedings of the European Nuclear Conference (ENC '05), Versailles, France. December 11-14, 2005, European Nuclear Society (ENS).

39. Parthasarathy, A., and C. D. Heising. 2004 Developing a set of profiles for a family of alliant energy circuit breakers. In EPRC Final Report. 2004, ISU Electric Power Research Center (EPRC).

40. Heising, C. D., and E. V. Steinfelds. 2004 Secure energy infrastructures: nuclear power plant security. In Proceedings of the 14th Pacific Basin Nuclear Conference (PBNC-14), Honolulu, Hawaii. March 21-25, 2004.

41. Heising, C. D., and M. Goodwin. 2004 Undergraduate engineering diversity course. In Proceedings of the American Society of Engineering Educators (ASEE) National Conference, Salt Lake City, Utah. June, 2004, American Society of Engineering Educators (ASEE).

42. Marathe, R., and C. D. Heising. 2003 Assessment of reliability and availability of mechanical components at a nuclear power plant. In Proceedings of the American Nuclear Society (ANS) National Meeting, San Diego, California. June 2003.

43. Daniel, S., and C. D. Heising. 2003 Impact of the organization on human reliability at the ft. calhoun nuclear power plant. In Proceedings of the American Nuclear Society (ANS) National Meeting, San Diego, California. June 2003.

44. Marathe, R., and C. D. Heising. 2003 Assessment of reliability and availability of mechanical components at ft calhoun nuclear power plant. In Proceedings of the Institute of Industrial Engineers (IIE) Research Conference, Portland, Oregon. May, 2003, Institute of Industrial Engineers (IIE).

45. Marathe, R., and C. D. Heising. 2003 Assessment of reliability and availability status of the chemical volume control system (CVCS) at the ft calhoun nuclear power plant. In Proceedings of the Iowa Academy of Science 2003 Meeting, Des Moines, Iowa. April 2003.

46. Heising, C. D., R. Marathe, and J. Gasper. 2002 Life cycle management and license renewal. In Proceedings of the ANS 2002 Utility Working Conference, Amelia Island, Florida. August 15, 2002, American Nuclear Society (ANS).

47. Heising, C. D., S. Daniel, and R. Marathe. 2002 Assessment of reliability and availability status of the chemical and volume control system. In Proceedings of the ANS Probabilistic Safety Assessment (PSA '02) Conference, Detroit, Michigan. October 6-10, 2002, American Nuclear Society (ANS).

48. Heising, C. D., R. Marathe, and S. Daniel. 2002 Life cycle management and aging at the Tt Calhoun nuclear power plant of OPPD. In Research Annual Report, ISU Electric Power Research Center (EPRC). June 2002, ISU Electric Power Research Center (EPRC).

49. Heising, C. D., K. M. Bryden, and S. Sharma. 2001 Virtual interactive maintenance of power equipment for training process. In 38th Annual Report of the ISU Electric Power Research Center (EPRC), 12-16. April 2001.

50. Rangarajan, A., and C. D. Heising. 2001 Statistical analysis to predict the electrical output for alliant energy. In Proceedings of the 8th Annual Conference on Industrial Engineering Theory, Applications and Practice, San Franciso, California. November 2001.

51. Heising, C. D., A. Rangarajan, and V. Saraogi. 2001 Applying statistical quality control at the columbia power plant. In 38th Annual Report of the ISU Electric Power Research Center (EPRC), 38, 6-11. April, 2001, ISU Electric Power Research Center (EPRC).

52. Heising, C. D., and A. Rangarajan. 2001 Statistical analysis to predict the power output for alliant energy. In Proceedings of the 6th Annual International

Conference on Industrial Engineering Theory, Applications and Practice, San Francisco, California. November 17, 2001.

53. Heising, C. D., and A. Kumar. 2001 Process monitoring of the ft calhoun reactor coolant pumps using artificial neural networks. In 38th Annual Report of the ISU Electric Power Research Center (EPRC), 38, 1-5. April, 2001, ISU Electric Power Research Center (EPRC).

54. Heising, C. D., E. B. Bartlett, and A. Kumar. 2000 Process monitoring of the ft. calhoun reactor coolant pumps using artificial neural networks. In 37th Annual Report of the ISU Electric Power Research Center (EPRC ), 223-229. April 2000.

55. Heising, C. D., K. M. Bryden, and S. Sharma. 2000 Application of virtual reality techniques to omaha public power district. In 37th Annual Report of the ISU Electric Power Research Center (EPRC), 37, 235-241. April 2000, ISU Electric Power Research Center (EPRC).

56. Heising, C. D., M. H. Yasin, and R. Krishnan. 2000 Applying statistical quality control at the columbia power plant. In 37th Annual Report of the ISU Electric Power Research Center (EPRC), 211-215. April, 2000, ISU Electric Power Research Center (EPRC).

57. Heising, C. D., and D. Srinivas. 1999 Seasonal variation analysis of the reactor coolant system at ft. calhoun nuclear power plant. In American Power Conference. April, 1999, American Power Conference.

58. Heising, C. D., R. Krishan, and Winarko. 1999 Applying statistical quality control at the columbia power plant. In 36th Annual Report of the ISU Electric Power Research Center (EPRC), 163-170. April 1999.

59. Heising, C. D., D. Subramainian, and N. Gopinath. 1999 Process monitoring of the reactor coolant pumps at the ft calhoun nuclear power plant. In 36th Annual Report of the ISU Electric Power Research Center (EPRC), 157-162. April 1999.

60. Heising, C. D., and A. Vaidyanathan. 1998 Combining statistical process control and reliability. In Proceedings of the 7th Annual Industrial Engineering Research Conference , Banff, Alberta, Canada. May 9-10, 1998, Institute of Industrial Engineers (IIE).

61. Heising, C. D. 1998 Statistical process control and capability analysis: industrial applications. In Proceedings of the Workshop on the Development of Science and Technology in Africa: Plans and Strategies, Durban, South Africa. July 27-31, 1998.

62. Heising, C. D. 1998 Seasonal variation analysis of the reactor coolant system at the ft calhoun nuclear power plant. In Proceedings of the International American Nuclear Society (ANS) Topical Meeting on the Safety of Operating Reactors, San Francisco, California. October 11-14, 1998.

63. Heising, C. D. 1998 Statistical analysis of the ft calhoun reactor coolant pump system. In Proceedings of the European Nuclear Congress (ENC-98), Nice, France. October 25-28, 1998, European Nuclear Society.

64. Heising, C. D., T. Konkimalla, and D. Subramainian. 1998 Statistical process control (SPC) at rock river electric generation station. In 35th Annual Report of the ISU Electric Power Research Center (EPRC), 73-86. April 1998.

65. Mirpuri, M., and C. D. Heising. 1997 Capability analysis applied to coal fired power plant boiler predictive maintenance. In Proceedings of the 6th Annual Industrial Engineering Research Conference (IERC'97), Miami, Florida. May 17-18, 1997.

66. Heising, C. D. 1997 Capability analysis applied to industrial applications. In Proceedings of the Fourth NSF Africa-USA International Conference on Manufacturing Technology, Pittsburgh, PA. April 11-14, 1997, National Science Foundation (NSF).

67. Heising, C. D. 1997 Overview of industrial applications of capability analysis. In Proceedings of the 8th Annual Industrial Engineering Research Conference ((IERC '97), Miami, Florida. May 17-18, 1997.

68. Heising, C. D. 1997 Statistical analysis of the ft. calhoun reactor coolant pump system. In International Nuclear Conference INC '97, Kuala Lumpur, Malaysia. October 26-28, 1997.

69. Heising, C. D., and A. Vaidyanathan. 1997 Combining statistical process control and reliability centered maintenance at the neal south coal fired power plant. In 34th Annual Report of the ISU Electric Power Research Center (EPRC). October 1997.

70. Heising, C. D., and M. Mirpuri. 1997 Statistical process control applied to a coal-fired power plant. In Proceedings of the 5th IIE Utilities and Energy Industries Conference, Orlando, Florida. February 24-25, 1997.

71. Mertz, K., and C. D. Heising. 1997 Capability analysis applied to high speed hole drilling. In Proceedings of the 6th Annual Industrial Engineering Research Conference (IERC-97), Miami, Florida. May 17-18, 1997.

72. Heising, C. D. 1997 Analyzing the reprocessing decision: plutonium recycle and nuclear proliferation. In ANS Transactions, Proceedings of the International ENS/ANS Conference, Hamburg, Germany, 31, 501-503. May 1997.

73. Patel, B., and C. D. Heising. 1997 Capability analysis applied to reactor coolant pump predictive maintenance. In Proceedings of the 8th Annual Industrial Engineering Research Conference, Miami, Florida. May 17-18, 1997, Institute of Industrial Engineers (IIE).

74. Heising, C. D., and M. Mirpuri. 1996 Statistical process control at neal south coal-fired station. In Electric Power Research Center (EPRC) 33rd Annual Report. May, 1996, ISU Electric Power Research Center (EPRC).

75. Patel, B., and C. D. Heising. 1996 Statistical analysis of the ft calhoun reactor coolant pump system. In Proceedings of the ANS International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technologies, Pennsylvannia State University, State College, PA. May 6, 1996.

76. Heising, C. D., and P. Bimal. 1996 Statistical control and artificial neural network analysis of ft calhoun reactor coolant pump system. In 33rd Annual

Report, ISU Electric Power Research Center (EPRC). May 1996, ISU Electric Power Research Center (EPRC).

77. Heising, C. D. 1996 Continuous improvement methods for the nuclear industry. In Proceedings of the Annual Society of Women Engineers (SWE) Conference, Portland, Oregon, Society of Women Engineers (SWE).

78. Mertz, K., and C. D. Heising. 1996 Capability analysis applied to hole drilling with high speed bits. In Proceedings of the Third NSF Africa-USA International Conference on Manufacturing Technology, Accra, Ghana. August 12-15, 1996, National Science Foundation (NSF).

79. Heising, C. D., and P. Bimal. 1996 Statistical analysis of the Ft. Calhoun reactor coolant pump system. In Proceedings of the 10th Pacific Basin Nuclear Conference (PBNC-10), Kobe, Japan. October 20-25, 1996, American Nuclear Society.

80. Heising, C. D., and B. Pimal. 1995 Statistical analysis of the ft calhoun reactor coolant pump system. In 32nd Annual Report of the ISU Electric Power Research Center (EPRC). May 1995, ISU Electric Power Research Center (EPRC).

81. Heising, C. D. 1995 Continuous improvement methods in the nuclear industry. In Proceedings of the International Topical Meeting Safety Culture in Nuclear Installations. April 24-28, 1995, International Atomic Energy Agency (IAEA), Vienna, Austria.

82. Bimal, P., and C. D. Heising. 1995 Statistical analysis of the ft calhoun reactor coolant pump system. In Proceedings of the International Conference on Probabilistic Safety Assessment Methodology and Applications, Seoul, Korea.

83. Dhanwada, C.V., and C. D. Heising. 1994 Fault identification by neural network recognition of CUSUM chart patterns. In ANS Transactions, Washington, DC.. November 13-16, 1994, American Nuclear Society (ANS).

84. Heising, C. D. 1994 Implementing total quality control in the nuclear utility industry. In Proceedings of the PSA/PRA and Severe Accidents Conference, Nuclear Society of Slovenia, Ljubljana, Slovenia. April 1994, Commission of the European Community.

85. Heising, C. D. 1994 The expectations of the young generation of nuclear experts. In European Nuclear Conference, Lyon, France. October 2-4, 1994, European Nuclear Society.

86. Heising, C. D., Z. Zheng, and W. S. Grenzebach. 1993 A model design for a reactor coolant pump system. In Proceedings of the Reliability Society 31st Annual Seminar. April 29, 1993, Boston IEEE Section.

87. Grenzebach, W. S., C. D. Heising, and T. J. Marx. 1993 Canonical correlation analysis of reactor coolant pump interaction. In Proceedings of the Second IASTED International Conference on Reliability, Quality Control and Risk Assessment, Cambridge, Massachusetts. 1993.

88. Grenzebach, W. S., C. D. Heising, and T. J. Marx. 1993 Canonical correlation analysis of the reactor coolant pump (RCP) and component cooling water

systems (CCWS). In Proceedings of the Probabilistic Safety Assessment International Topical Meeting (PSA '93), San Francisco, California. 1993.

89. Heising, C. D., Z. Zhang, and W. S. Grenzebach. 1993 A model design for a reactor coolant pump. In Proceedings of the 4th Annual Scientific and Technical Conference of the Nuclear Society International/Moscow, Nizhni Novgorod, Russia. June 28- July 2, 1993.

90. Heising, C. D. 1992 Statistical analysis of reactor systems for improved operations and maintenance. In 8th Power Plant Dynamics, Control and Testing Symposium, University of Tennessee, Knoxville, Tennessee. May 27-29, 1992.

91. Grenzebach, W. S., C. D. Heising, and T. J. Marx. 1992 Regression analysis of the component cooling water system and the reactor pump system. In Proceedings of the International Conference on the Design and Safety of Advanced Nuclear Power Plants.

92. Rodriguez, A., and C. D. Heising. 1992 Statistical process control methods. In Systems Analysis for Process Improvement (SAPI) Model13. August 1992, U.S. Department of the Navy (DoN), Naval Personnel Research and Development Center (NPRDC), San Diego, California.

93. Heising, C. D., and D. Luciani. 1991 Implementing total quality control in the nuclear power industry. In Proceedings of the American Power Conference (APC), American Power Conference (APC).

94. Grenzebach, W. S., C. D. Heising, and T. Marx. 1991 Maximum likelihood factor analysis of the reactor coolant pump system. In ANS International Topical Meeting on the Safety of Thermal Reactors, Portland, Oregon. 1991, American Nuclear Society (ANS).

95. Grenzebach, W. S., C. D. Heising, and T. Marx. 1991 Regression analysis of the reactor coolant system. In Proceedings of the International Power Generation Conference, ASME Paper 91-JPGC-NE-8, San Diego, California. October 6-10, 1991.

96. Heising, C. D., and W. S. Grenzebach. 1991 Statistical analysis of reactor systems for improved operations and maintenance. In Second International Conference on Nuclear Power Plant Safety and Personnel Training. 1991, Obninsk Atomic Research Center, Obninsk, Russia.

97. Heising, C. D., and W. S. Grenzebach. 1990 A computerized diagnostic system for nuclear power plant control rooms based on statistical quality control. In Proceedings of the ANS Topical Meeting on Advances in Human Factors Research on Man/Computer Interactions. 1990.

98. Kim, J., C. D. Heising, M. Silevitch, and B. Naka. 1990 Intelligent risk assessment/simulation model. In Interim Report, Office of the Secretary of Defense (SOD), Washington, D.C.. June 1990, Northeastern University, Boston, Massachusetts USA.

99. Heising, C. D. 1988 Courses in risk analysis at the undergraduate and graduate levels. In Proceedings of the ASME National Conference, Chicago, Illinois; Session: Risk Training in Engineering Curricula. November 30, 1988.

100. Heising, C. D., W. S. Grenzebach, D. L. Luciani, M. Sato, and S. Melhem. 1988 Methods for the computerized control of nuclear power plants for improved safety, quality and productivity. In Final Report, Department of Energy (DoE) Contract, Northeastern University, Boston, Massachusetts. December 1988.

101. Heising, C. D. 1988 Total quality control: computerized nuclear power plant control rooms. In Proceedings of the Joint ORSA/TIMS Meeting, Washington, DC. April 25, 1988, ORSA/TIMS.

102. Heising, C. D. 1987 Controlling hazardous technologies. In Proceedings of the Institute of Industrial Engineers (IIE), Washington, D.C.. May 17, 1987, Institute of Industrial Engineers (IIE).

103. Heising, C. D., D. L. Wetherell, S. A. Melhem, and M. Sato. 1987 Total quality control: the deming management philosophy applied to nuclear power plants. In Proceedings of the International Conference on Quality Control, ASQC/JUSE, Tokyo, Japan. October 20-23, 1987, American Society of Quality Control (ASQC); Japanese Union of Scientists and Engineers (JUSE).

104. Heising, C. D., D. L. Wetherell, S. Melhem, and M. Sato. 1987 Total quality control: the deming management philosophy applied to nuclear power plants. In Proceedings of the IASTED International Conference on Quality Control and Reliability, University of California, Los Angeles. 1987.

105. Heising, C. D., and N. Shwayri. 1987 Assessing the risk-cost-benefits of electric power life extension. In Proceedings of the International Conference on Probabilistic Safety Assessment and Risk Management, Zurich, Switzerland, European/American/Swiss Nuclear Societies.

106. Heising, C. D., D. L. Wetherell, S. Melhem, and M. Sato. 1987 Total quality control: the deming management philosophy applied to nuclear power plants. In ANS Transactions, Los Angeles, California. November 15-19, 1987, American Nuclear Society (ANS).

107. Heising, C. D., and N. Shwayri. 1987 An application of the two-stage bayesian method to estimate the outage rate of oil-fired boilers. In Proceedings of the IXth International Conference on Production Research. August 17-20, 1987, University of Cincinnati.

108. Heising, C. D., and N. Shwayri. 1986 Data analysis of fossil fuel power plant components for life extension and improved availability. In Final Report, Ed. Boston Edison Company. September 1986, Northeastern University,boston, Massachusetts.

109. Guey, C. N., and C. D. Heising. 1985 Development of a common-cause failure analysis method: the inverse stress - strength interference technique. In Proceedings of the Fourth International Conference on Structural Safety and Reliability, Kobe, Japan. May 27-29, 1985.

110. Heising, C. D. 1985 A decision aid on decontamination for wing commanders under chemical attack conditions. In Final Report, USAF Brooks Air Force Base, San Antonio, Texas. January 1985.

111. Heising, C. D., S. Malone, and F. Chine. 1985 Methods for reliability warrant verification. In Report for U.S. Air Force Summer Faculty Research Program, Hanscom AFB, Boston, MA. August 1985.

112. Heising, C. D., and H. Inhaber. 1985 A comparison of regional and global catastrophic hazards associated with energy technologies. In Proceedings of the International Symposium on the Risks and Benefits of Energy Systems, Julich near Aachen, Germany. April 1985, International Atomic Energy Agency (IAEA).

113. Heising, C. D. 1985 Developing methods for the computerized control of large, technological systems for improved safety, quality and productivity. In Final Report, GE/CIEM Grant Program. June, 1985, Northeastern University.

114. Schechtman, R., and C. D. Heising. 1985 Risk assessment of the beneficial impact of a filtered venting containment system in a PWR with large, dry containment. In ANS Transactions, Boston, Massachusetts, 48, American Nuclear Society (ANS).

115. Heising, C. D., and J. I. Choi. 1985 Consideration of dependent failures in redundancy optimization problems with multiple constraints. In Proceedings of the ANS Conference on Nuclear Power Plant Aging, San Diego, California. July 8-11, 1985, American Nuclear Society (ANS).

116. Heising, C. D., and V. P. George. 1985 An estimate of the economy wide financial risk associated with a severe nuclear accident. In Proceedings of the ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, San Francisco, California. 1985, American Nuclear Society (ANS).

117. Heising, C. D. 1985 Risk assessment in the regulatory arena: controlling hazardous technologies. In Proceedings of the Institute of Industrial Engineers (IIE) National Conference, Chicago, Illinois, 494-500. December 8-11, 1985.

118. Guey, C. N., and C. D. Heising. 1985 The inverse stress-strength interference (ISSI) method for common cause analysis. In Proceedings of the International ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, San Francisco, CA. February 24-28, 1985.

119. Heising, C. D. 1985 The treatment of uncertainty in probabilistic risk assessment (PRA)-- safety goals, levels of analysis, and expert opinion. In Proceedings of the International Atomic Energy Agency (IAEA) Symposium on the Implications of Probabilistic Risk Assessment (PRA), Blackpool, United Kingdom (UK). March, 1985.

120. Heising, C. D. 1984 Motivating women to seek careers in the nuclear industry. In ANS Transactions, New Orleans, LA, 46, 32. June 3-7, 1984, American Nuclear Society.

121. Plys, M., R. E. Henry, and C. D. Heising. 1984 EROS: a core concrete interaction model. In American Nuclear Society (ANS) Transactions, Washington, D.C., 47, 323-324. November 11-16, 1984.

122. Heising, C. D., and H. Inhaber. 1984 A comparison of regional and global catastrophic hazards associated with energy technologies. In American Nuclear

Society (ANS) Transactions, Washington, DC, 47, 25-27. November 11-16, 1984.

123. Heising, C. D. 1984 Financial risk assessment of large scale projects. In Transactions of the Symposium on Risk Management, World Bank, Washington, DC. May 24-25, 1984, World Bank.

124. Guey, C. N., and C. D. Heising. 1984 A method for estimating common cause failure probability and model parameters: the inverse stress-strain interference (ISSI) technique. In MIT-EL-84-010. July 1984, Energy Laboratory, Massachusetts Institute of Technology (MIT).

125. Plys, M., C. D. Heising, and R. Henry. 1983 Simulant fluid experiments for core-concrete thermal attack. In Transactions of the ANS/ENS Topical Meeting on Severe Reactor Accidents, Cambridge, Massachusetts. August 1983, American Nuclear Society (ANS).

126. Heising, C. D., and E. I. Patterson. 1983 Plant specification of human error through a two-stage bayesian procedure. In ANS Transactions, Detroit, MI, 44. June 1983, American Nuclear Society.

127. Heising, C. D., H. Lipschitz, and M. S. Brown. 1983 Uncertainty analysis in risk studies of high level waste repositories. In Final Report. July 1983, Sandia National Laboratory, Albuquerque, New Mexico.

128. Heising, C. D., and V. L. Oliveria. 1983 A unified approach for calculating the core melt frequency due to internal and external initiating events. In ANS Transactions, San Francisco, CA, 45, 303-310. November, 1983, American Nuclear Society (ANS).

129. Heising, C. D., and H. Inhaber. 1982 A comparison of regional and global catastrophic hazards associated with energy technologies. In Proceedings of the SFRP Annual Conference, Xth Regional Conference of the IRPA, "Comparison of Risks from Major Human Activities", Avignon, France. 1982.

130. Lee, M., M. S. Kazimi, G. Brown, C. D. Heising, J. Meyer, D. Medek, S. Mohammed, M. Plys, R. Sehgall, and C. Tsai. 1982 Aspects of severe light water reactor accident analysis. In Final Report, Department of Nuclear Engineering, MIT. August, 1982.

131. Heising, C. D., N. C. Rasmussen, and C. Mak. 1982 Common cause analysis: a review and extension of existing methods. In Final Report. October, 1982, Nuclear Engineering Department, Massachusetts Institute of Technology (MIT), Cambridge, Massachusetts.

132. Burke, R. P., C. D. Heising, and D. C. Aldrich. 1982 In plant considerations for offsite emergency response to reactor accidents. In NUREG/CR-2925, SAND82-2004, Sandia National Laboratory, Albuquerque, New Mexico. December 1982.

133. Heising, C. D., and S. C. Dinsmore. 1982 A method for improving accident sequence recognition in nuclear power plant control rooms. In Transactions of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, Chicago, Illinois. August 30- September 2, 1982, American Nuclear Society (ANS).

134. Heising, C. D., E. Frankel, E. VanMarcke, and H. Irwig. 1982 Engineering failures: man-made. In Proceedings of the SFRP Annual Congress Xth Regional Conference of the IRPA, Comparison of Risks Resulting from Major Human Activities, Avignon, France. October 22-26, 1982.

135. Heising, C. D., R. Karimi, C. Mak, M. Modarres, N. C. Rasmussen, and L. Wolf. 1981 User's manual for MOCUS-BACFIRE: a computer program for common cause failure analysis. In MIT-EL-81-034. November 1981, MIT Electric Utility Program.

136. Carlson, D., and C. D. Heising. 1981 Organization for the performance of PRA programs. In Transactions of the International ANS/ENS Topical Meeting on Probabilistic Risk Assessment, Port Chester, New York. September 20-24, 1981, American Nuclear Society (ANS).

137. Schechtman, R., and C. D. Heising. 1981 Analysis of filtered venting as a mitigation safety feature in PWRs with large, dry containments. In Transactions of the ANS/ENS Topical Meeting on Probabilistic Risk Assessment, Port Chester, NewYork. 1981, American Nuclear Society (ANS).

138. Heising, C. D. 1981 Generic nuclear safety issues: methods and examples. In Transactions of the International ANS/ENS Topical Meeting on Probabilistic Risk Assessment, Port Chester, New York. September 20-24, 1981.

139. Heising, C. D. 1981 The use of PRA techniques to assess and improve reactor operations. In ANS Transactions, San Francisco, CA, 39, 859. November 1981.

140. Mak, C., C. D. Heising, and M. Modarres. 1981 Application and extension of the MOCUS-BACFIRE common cause analysis code for reactor safety systems. In Transactions of the International ANS/ENS Topical Meeting on Probabilistic Risk Assessment (PRA), Port Chester, New York. 1981, American Nuclear Society (ANS).

141. Heising, C. D. 1981 The determination of plant status during abnormal reactor operating conditions: accident sequence identification. In . July, 1981, NUREG/CR-2293, SANDIA81-1774, Sandia National Laboratory.

142. Heising, C. D. 1981 Supply of appropriate nuclear technology for the developing world: small power reactors for electricity generation. In Proceedings of the International Conference on Nuclear Technology in Developing Countries: Problems and Prospects, Trieste, Italy. 1981.

143. Heising, C. D., and J. Lepervanche-Valencia. 1980 A probabilistic assessment of containment inerting in boiling water reactors (BWRs). In Transactions of the International Atomic Energy Agency (IAEA) Conference on Current Nuclear Power Plant Safety Issues, Stockholm, Sweden. October, 1980.

144. Heising, C. D. 1980 Plutonium denaturing: how effective a safeguards deterrent?. In Proceedings of the Institute for Nuclear Materials Management (INMM) National 21st Annual Meeting, Palm Beach, Florida. July 1-2, 1980.

145. Heising, C. D. 1980 Generic nuclear safety issues: methods of analysis. In MIT-NE-241. September 1980, MIT : Nuclear Engineering Department.

146. Heising, C. D. 1979 Social decision analysis: an application to the plutonium nuclear policy question. In Transactions of the TIMS/ORSA meeting, Session on Frontiers in Decision Analysis, New Orleans, LA. April 30- May 2, 1979, TIMS/ORSA.

147. Heising, C. D. 1979 International arrangements for spent fuel reprocessing: the view from developing countries. In ANS Transactions, Atlanta, Georgia, 32, 365. June, 1979, American Nuclear Society (ANS).

148. Heising, C. D., I. Saragossi, and P. Sharafi. 1979 A comparative assessment of the LMFBR and advanced converter fuel cycles. In Proceedings of the ASME-ASEE Joint Power Generation Conference, Charlotte, North Carolina. October 7-11, 1979, ASME.

149. Heising, C. D. 1979 Quantifying the relative diversion resistance and economics of alternative fuel cycles. In ANS Transactions, San Francisco, California, 33, 446-447. November, 1979.

150. Heising, C. D. 1978 Applying bayesian decision theory to assess reprocessing economic and social cost-benefits. In Transactions of the American Nuclear Society (ANS) Topical Meeting on the Probabilistic Analysis of Nuclear Reactor Safety, Los Angeles, California, 2, IV.3-1/3-10. May 8, 1978.

151. Heising, C. D. 1978 Analyzing the reprocessing decision: plutonium recycle and nuclear proliferation. In Proceedings of the Institute for Nuclear Materials Management (INMM Journal), VII, 91-110. June 1978.

152. Heising, C. D. 1977 Analyzing the reprocessing decision: plutonium recycle and nuclear proliferation. In ANS Transactions, San Francisco, CA, 27, 452-453, American Nuclear Society (ANS).

153. Heising, C. D. 1977 Plant location and transportation models in the light-water reactor fuel cycle. In Transactions of the TIMS/ORSA Meeting, San Francisco, California. May 9-11, 1977.

Bulletins, Reports, or Conference Proceedings: Non-Refereed

154. Balasubramainian, V. R., and C. D. Heising. 2003 Vulnerability risk assessment of the iowa state university power plant. In Final report. November, 2003, Industrial and Manufacturing Systems Engineering (IMSE) Department, Iowa State University, Ames, Iowa.

Books: Authored or Co-Authored

155. Heising, C. D. The reprocessing decision: a study in policy making under uncertainty. 1979. The Reprocessing Decision: A Study in Policy-Making Under Uncertainty (in Outstanding Dissertations on Energy Series). Garland Publishing, Inc..

Books: Edited or Co-Edited

156. 2009. Risk Management. Safeguards Considerations of Thorium Utilization in Nuclear Reactor Fuel Cycles. American Nuclear Society. In Press.

Book Chapters/Sections

157. Heising, C. D. July 1983 Reliability analysis and probabilistic risk assessment In Risk Assessment for Ranking Energy Technologies. Ed., Herbert Inhaber

158. Heising, C. D. 1982 Quantitative methods in research and development decision making In The Research System in the 1980s Public Policy Issues. Ed., John M. LongsdenThe Franklin Institute Press, Philadelphia, PA

159. Baybutt, P., C. D. Heising, A. E. Bassioni, G. W. Parry, and R. Iman. 1982 Treatment of uncertainties In Probabilistic Risk Assessment Procedures Guide, Chapter 13. Nuclear Regulatory Commission (NRC), Washington, DC

160. Heising, C. D. 1981 Social decision analysis: an application to the plutonium nuclear policy question In Applications of Management Science. Ed., Randall L. Schultz1, JAI Press, Inc., Greenich, Connecticut

PRESENTATIONS Presentations: Invited

1. Heising, C.D.. 2009. Thorium and Alternatives. , Department Seminar Series, September 25, 2009, Nuclear Engineering Department, University of Michigan, Ann Arbor, Michigan.

2. Heising, C. D.. 2009. "Safeguards Considerations of Thorium Utilization in Nuclear Reactor Fuel Cycles". . Department Seminar Series, Department of Nuclear Engineering, April 6, 2009, UC Berkeley.

3. Heising, C.D.. 2009. "Closing the Nuclear Fuel Cycle: Thorium and Advanced Alternatives". . Presented work on sabbatical leave to the MHR group (sponsors), Modular Helium Reactor (MHR) Group, June 4, 2009, General Atomics Company, San Diego, California.

4. Heising, C.D.. 2008. "Safety Engineering". , IE 501 Lecture, January 23, 2008, Iowa State University, Ames, Iowa, USA.

5. Heising, C.D.. 2008. "Safety Engineering". , Engineering Studies (ES) 260, March 7, 2008, Iowa State University, Ames, Iowa, USA.

6. Heising, C.D.. 2008. "Safety Engineering". , Qatar University College of Engineering, January 16, 2008, Doha, Qatar.

7. Heising, C. D. 2007. Women in engineering. , Seminar at Qatar University at the Women's College, March 12, 2007, Doha, Qatar.

8. Heising, C. D. 2005. Vulnerability risk assessment. , Nuclear Science and Engineering Institute, University of Missouri, July 13, 2005, Columbia, Missouri USA.

9. Heising, C. D. 2003. Vulnerability risk assessment for homeland security. , Nuclear Engineering Department, University of Missouri, Rolla, October 23, 2003, Rolla, Missouri USA.

10. Heising, C. D. 2003. Vulnerability risk assessment for homeland security. , Mechanical and Industrial Engineering Department, November 13, 2003, University of Iowa, Iowa City, Iowa USA.

11. Heising, C. D. 2002. Life cycle management and license renewal: a case study of the ft calhoun nuclear power plant. , ANS 2002 Utility Working Conference, August 2002, Amelia Island, Florida.

12. Heising, C. D. 2001. Statistical analysis to predict the power output for alliant energy. , 6th Annual Conference on Industrial Engineering Theory, November 2001, San Francisco, CA.

13. Heising, C. D. 1998. Status of women engineering faculty: facts and personal reflections. , Engineering Foundation Conference: Creating New Paradigms for Developing and Retaining Women Engineers, July 14-18, 1998, Club Tremblant near Montreal, Canada.

14. Heising, C. D. 1997. Capability analysis applied to high speed hole drilling. , Industrial Engineering Department, University of Stellenbosch, February 24, 1997, Stellenbosch, South Africa.

15. Heising, C. D. 1997. Teaching professional survival skills to women engineering students. , ISU Program for Women in Science and Engineering (PWSE), March 19, April 15, October 1 and November 5, 1997, Ames, Iowa USA.

16. Heising, C. D. 1996. Teaching professional survival skills to women engineering students. , Women in Engineering Program Advocates Network (WEPAN) National Conference, June 2-4, 1996, Denver, Colorado USA.

17. Heising, C. D., and P. Bimal. 1996. Statistical analysis of the ft calhoun reactor coolant pump system. , 10th Pacific Basin Nuclear Conference (PBNC-10, October 20-25, 1996, Kobe, Japan.

18. Heising, C. D. 1996. Welcoming Address. , Second ANS-ASEE University Working Conference, June 14, 1996, Reno, Nevada USA.

19. Heising, C. D. 1996. Statistical process control applied to nuclear power plants. , Nuclear and Industrial Engineering Departments, Texas A&M University, October 1, 1996, College Station, Texas, USA.

20. Heising, C. D. 1996. Preventive maintenance and condition monitoring. , American Nuclear Society (ANS) Professional Development Workshop, ANS National Meeting, November 1996, Washington, D.C..

21. Heising, C. D. 1996. My life as a woman engineer. , Invited seminar, Iowa State University (ISU) Archives of Women in Science and Engineering, March 20, 1996, Iowa State University, Ames, Iowa.

22. Heising, C. D. 1995. Teaching professional survival skills to women engineering students. , ISU Program for Women in Science and Engineering (PWSE), October 18 and November 15, 1995, Ames, Iowa USA.

23. Heising, C. D. 1995. Women in engineering. , NSF Workshop, Teaching Survival Skills and Ethics to Emerging Scientists, May 18-21, 1995, West Virginia.

24. Heising, C. D. 1994. Business process re-engineering: radical change. , American Society of Quality Control (ASQC) Local Section Meeting, March 8, 1994, Ames, Iowa USA.

25. Heising, C. D. 1994. Total quality management applied to nuclear power plants. , Mechanical Engineering Department, Iowa State University (ISU), March 3, 1994, Ames, Iowa USA.

26. Heising, C. D. 1993. Total quality management (TQM) applied to nuclear power plants. , Industrial and Manufacturing Systems Engineering (IMSE) Department, April 19, 1993, Ames, Iowa USA.

27. Heising, C. D. 1993. Total quality management: success stories in US industry. , Alpha Pi Mu Student Honor Society Chapter, Industrial Engineering and Manufacturing Systems (IMSE) Department, Iowa State University of Science and Technology, October 26, 1993, Ames, Iowa USA.

28. Heising, C. D. 1992. Total quality management (TQM) applied to nuclear power plants. , North Anna Nuclear Power Plant, Virginia Power Company (VEPCO), October 13, 1992, North Anna, Virginia USA.

29. Heising, C. D. 1992. Statistical quality control applied to nuclear power plants. , Woodruff School of Mechanical Engineering, Georgia Institute of Technology, January 23, 1992, Atlanta, Georgia USA.

30. Heising, C. D. 1992. Nuclear power in russia. , American Society of Mechanical Engineers (ASME), Student Chapter, Northeastern University, February 20, 1992, Boston, Massachusetts USA.

31. Heising, C. D. 1992. Nuclear power in russia. , Northeastern Section of the American Nuclear Society (ANS), March 25, 1992, Newton, Massachusetts USA.

32. Heising, C. D. 1992. Meeting the japanese challenge: quality, reliability, and risk-industrial management in the 1990s and beyond. , Industrial Engineering and Information Systems (IEIS) Department, Northeastern University, April 23, 1992, Boston, Massachusetts USA.

33. Heising, C. D. 1992. Environmental issues and their effects on nuclear policy. , American Nuclear Society (ANS) national meeting, Professional Women in ANS (PWANS) seminar, June 8, 1992, Boston, Massachusetts USA.

34. Heising, C. D. 1992. Total quality management: success stories in US industry. , Naval Personnel Research and Development Center (NPRDC), September 3, 1992, San Diego, California.

35. Heising, C. D. 1992. Total quality management (TQM) success stories in US industry. , College of Engineering, Hong Kong Universityof Science and Technology (HKUST), November 25, 1992, Kowloon, Hong Kong, China.

36. Heising, C. D. 1991. Management in a scientific laboratory. , Ames Laboratory, Iowa State University, December 13, 1991, Ames, Iowa USA.

37. Heising, C. D. 1991. Statistical quality control applications in the nuclear industry. , Industrial Engineering Department, University of Florida, March, 1991, Gainesville, Florida USA.

38. Heising, C. D. 1991. Nuclear power in the soviet union after chernobyl. , Society of Women Engineers (SWE), Northeastern University, November 4, 1991, Boston, Massachusetts USA.

39. Heising, C. D. 1990. Risk assessment for technology transition. , Pentagon, April 24, 1990, Washington, DC.

40. Heising, C. D. 1990. Risk assessment for technology transition. , Navy/DARPA, May 8, 1990, Washington, DC.

41. Heising, C. D. 1990. Industrial engineering and information systems at northeastern university: a plan for survival in the 1990s. , Industrial Engineering and Information Systems Department, Northeastern University, May 22, 1990, Boston, Massachusetts USA.

42. Heising, C. D. 1990. Nuclear safety research. , Nuclear Engineering Department, University of Florida, September 24, 1990, Gainesville, Florida USA.

43. Heising, C. D. 1990. Statistical quality control applied to nuclear power operations. , Nuclear Engineering Sciences Department, University of Florida, December 6, 1990, Gainesville, Florida USA.

44. Heising, C. D. 1990. Industrial engineering: discipline of the future. , College of Engineering, Southern Illinois University, March 16, 1990, Edwardsville, Illinois USA.

45. Heising, C. D. 1990. Industrial engineering: discipline of the future. , University of Toledo College of Engineering, April 6, 1990, Toledo, Ohio USA.

46. Heising, C. D. 1990. Reliability trends: calculation vs application. , 28th Annual Spring Reliability Seminar, Boston IEEE Reliability Chapter, April 19, 1990, Boston, Massachusetts.

47. Heising, C. D. 1989. Risk evaluation of technological system transition. , Industrial Advisory Board Meeting, Center for Electromagnetic Research, Northeastern University, May 2, 1989, World Trade Center, Boston, Massachusetts USA.

48. Heising, C. D. 1989. Total quality management: success stories in US industry. , U.S. Army conference, May 9, 1989, Fort Monmouth, New Jersey, USA.

49. Heising, C. D. 1988. Discover the secret of japanese corporations: their competitive edge. , Northeastern University Society of Women Engineers (SWE) Section Meeting, October 27, 1988, Boston, Massachusetts USA.

50. Heising, C. D. 1988. Methods for the computerized control of nuclear power plants: total quality control. , Department of Mechanical Engineering Seminar Series, University of Delaware, March 18, 1988, Newark, Delaware USA.

51. Heising, C. D. 1988. Risks of nuclear power. , Debate with Dr. Gordon Thompson, Union of Concerned Scientists, December 8, 1988, Worcester, Massachusetts USA.

52. Heising, C. D. 1988. Placing a value on human life. . Presentation at the joint AMITA/SWE conference held at MIT., AMITA/SWE Symposium: AMITA is the Alumane Association of MIT, and SWE is the Society of Women Engineers., April 9, 1988, Massachusetts Institute of Technology (MIT).

53. Heising, C. D. 1988. The chernobyl incident: long range effects of risk assessment technology in the USSR and USA. , Iowa State University (ISU) College of Engineering Seminar, April 5, 1988, Ames, Iowa USA.

54. Heising, C. D. 1988. Taking the road less travelled: engineering careers for women. , Iowa State University, Program for Women in Science and Engineering (PWSE), April 16, 1988, Ames, Iowa USA.

55. Heising, C. D. 1988. The deming management method applied to nuclear power plants. , Vermont Yankee Nuclear Power Plant, September 22, 1988, Vernon, Vermont USA.

56. Heising, C. D. 1988. Risk assessment: controlling hazardous materials. , World Bank, October 19, 1988, Washington, D.C..

57. Heising, C. D. 1988. Expert systems for nuclear power plant control. , Industrial Engineering/Information Systems (IE/IS) Department Seminar, Northeastern University, October 27, 1988, Boston, Massachusetts.

58. Heising, C. D. 1988. Methods for the computerized control of nuclear power plants. , Department of Energy (DOE) Headquarters, March 17, 1988, Germantown, Maryland USA.

59. Heising, C. D. 1987. The chernobyl accident. , Boston Edison Company, Pilgrim Nuclear Power Plant, January 21, 1987, Plymouth, Massachusetts USA.

60. Heising, C. D. 1987. Chernobyl accident: report from kurchatov institute. , Long Beach State University, March 26, 1987, Long Beach, California USA.

61. Heising, C. D. 1987. Safety of maine yankee nuclear power plant. , American Association of University Women (AAUW) Forum, University of Maine, October 4, 1987, Augusta, Maine.

62. Heising, C. D. 1987. Probabilistic risk assessment of boiler water reactor inerting systems and human reliability. , Atomic Energy of Canada, Ltd (AECL), January 14, 1987, Toronto, Canada.

63. Heising, C. D. 1987. Applications of japanese management methods to nuclear power plants. . Invited seminar, Joint Industrial Engineering/Nuclear Engineering department invited seminar, The Pennsylvannia State University (Penn State), October 8, 1987, State College, Pennsylvannia, USA.

64. Heising, C. D. 1987. Introduction to human reliability analysis and the double bayesian updating approach for human error rate prediction and chernobyl nuclear power plant accident: report from the kurchatov institute. , Kansai Electric Company Central Headquarters, 1987, Osaka, Japan.

65. Heising, C. D. 1987. Nuclear safety: reality or myth?. . Keynote speaker with honorarium, Series on Science, Technology and Human Values, Regis College, December 7, 1987, Weston, Massachusetts USA.

66. Heising, C. D. 1987. History, present condition and future of PRA and risk management in the united states. , Gakushi-Kaikan, Japanese Engineers, October 21, 1987, Tokyo, Japan.

67. Heising, C. D. 1987. Use of statistical quality control methods in nuclear power plants. , Florida Power and Light Company, December 16, 1987, Juno Beach, Florida.

68. Heising, C. D. 1987. Probabilistic risk assessment applied to nuclear power plants. , Korea Power Company, October 26, 1987, Seoul, Korea.

69. Heising, C. D. 1986. An introduction to risk assessment and case study: USAF system reliability. , Computer Science and Management Courses, Northeastern University, August 28, 1986, Boston, Massachusetts.

70. Heising, C. D. 1986. The nuclear power program in the USSR and eastern bloc countries. , Invited seminar presentation at the Oak Ridge National Laboratory (ORNL), November 6, 1986, Oak Ridge, Tennessee, USA.

71. Heising, C. D. 1986. Probabilistic risk assessment. , Soviet Union: USSR Safety Regulatory Agency, Hungarian Academy of Sciences, September 10, 1986, Moscow, Russia and Budapest, Hungary.

72. Heising, C. D. 1986. Is nuclear energy safe?. , Symposium on Nuclear Energy, Norfolk District Medical Society, October 23, 1986, Foxboro, Massachusetts USA.

73. Heising, C. D. 1986. Risks of nuclear energy: the impact of chernobyl on the soviet union nuclear power program and seabrook station. , Department of Nuclear Engineering, University of Massachusetts, December 1, 1986, Lowell, Mass..

74. Heising, C. D. 1986. Risks of nuclear energy: the impact of chernobyl. , The Network, Boston Women Professionals Group, November 20, 1986, Boston, Massachusetts USA.

75. Heising, C. D. 1986. The use of bayesian statistics in reliability studies: predicting USAF system performance. , Northeastern University, May 7, 1986, Boston, Massachusetts USA.

76. Heising, C. D. 1986. Double bayesian analysis methods applied to human reliability and estimate of boiler unavailability. , DNE/Engineering Technology Division, Brookhaven National Laboratory, December 19, 1986, Upton, Long Island, New York.

77. Heising, C. D., and A. Foster. 1986. Chernobyl nuclear power plant accident. , ASME special lecture, Northeastern University, May 9, 1986, Boston, Massachusetts.

78. Heising, C. D. 1986. Nuclear power in china and the soviet union. , Society of Women Engineers (SWE), Boston Section, December 14, 1986, Boston, Massachusetts USA.

79. Heising, C. D. 1986. Chernobyl nuclear power plant accident. , Northeastern Section of the American Nuclear Society (ANS), May 15, 1986, Rowe, Massachusetts USA.

80. Heising, C. D. 1985. The use of PRA in design. . Reactor safety delegation to China organized by the American Nuclear Society (ANS). Dr. Richard Leahy, Chair, Nuclear Engineering Department, RPI, Troy, NY delegation leader.,

Chinese Association for Science and Techology (CAST, November 1985, Beijing, Chengdu, and Shanghai, The People's Republic of China.

81. Heising, C. D. 1985. Risk analysis: nuclear and non-nuclear applications. , IEIS Department Colloquium, Northeastern University, May 6, 1985, Boston, Massachusetts USA.

82. Heising, C. D. 1985. Living and larning with risk assessment. , Northeastern Section, American Nuclear Society (ANS), 1985, Boston, Massachusetts USA.

83. Heising, C. D. 1985. Total quality management applied to the nuclear industry. , Department Colloquium, Industrial Engineering Department, Northeastern University, May 6, 1985, Boston, Massachusetts USA.

84. Heising, C. D. 1984. Comparative risks of energy technologies. , Risk Management Group, CIS, Massachusetts Institute of Technology (MIT), May 7, 1984, Cambridge, Massachusetts USA.

85. Heising, C. D. 1984. Comparative risks of energy technologies. , Risk Management Group, CIS, Massachusetts Institute of Technology (MIT), May 7, 1984, Cambridge, Massachusetts USA.

86. Heising, C. D. 1984. Probabilistic risk assessment. , Technical Program Committee for the 5th International Meeting on Thermal Reactor Safety, European Nuclear Society (ENS), Karlsruhe Laboratory, September 9, 1984, Karlsruhe, Federal Republic of Germany.

87. Heising, C. D. 1983. Reactor safety and three mile island. , Center for Advanced Engineering Studies (CAES), Advanced Study Program, Massachusetts Institute of Technology (MIT), May 3, 1983, Cambridge, Massachusetts USA.

88. Heising, C. D. 1983. Matrix formulation of a utility financial risk model for nuclear power plant severe accidents. , Pickard, Lowe and Garrick, Inc., March 24, 1983, Newport Beach, California USA.

89. Heising, C. D. 1983. Matrix formulation of a utility financial risk model for nuclear power plant severe accidents: TVA project. , Pickard, Lowe and Garrick, InC, March 24, 1983, Irvine, California USA.

90. Heising, C. D. 1983. Reactor safety and three mile island. , Center for Advanced Engineering Studies (CAES),Advanced Study Program, Massachusetts Institute of Technology (MIT), May 3, 1983, Cambridge, Massachusetts USA.

91. Heising, C. D. 1982. Updating the core melt frequency using bayes' theorem and ORNL precursor data. , Pickard, Lowe and Garrick, Inc., October, 1982, Irvine, California USA.

92. Heising, C. D. 1982. The MIT research program in probabilistic risk assessment for nuclear power applications. , ILO Symposium on Systems Reliability and Risk Assessment, MIT, November 16, 1982, Cambridge, Massachusetts USA.

93. Heising, C. D. 1982. Applications of bayesian methods to reactor safety studies: an assessment of hydrogen control methods in mark-I boiling water reactors (BWRs). , Department of Nuclear, Chemical and Thermal Engineering, University of California, January 11, 1982, Los Angeles, California USA.

94. Heising, C. D. 1982. Career opportunities in nuclear engineering. , Renssalaer Polytechnic Institute (RPI) Student Section of the American Nuclear Society (ANS) and the Northeast New York ANS Section, April 19, 1982, Troy, New York USA.

95. Heising, C. D. 1982. A probabilistic risk assessment of hydrogen control in BWRs. , Department of Nuclear Engineering, RPI, April 19, 1982, Troy, NY USA.

96. Heising, C. D. 1982. Reliability and risk assessment. , Nuclear Engineering Department, MIT, May 6, 1982, Cambridge, Massachusetts USA.

97. Heising, C. D. 1982. Plutonium denaturing: economic aspects, operations research approach. , University of Illinois Arms Control Symposium, Argonne National Laboratory, April 24, 1982, Argonne, Illinois USA.

98. Heising, C. D. 1982. Risk assessment for large, technological systems. , Ocean Engineering Department, October 19, 1982, Cambridge, Massachusetts USA.

99. Heising, C. D. 1982. Reliability analysis of chemical engineering facilities: an example. , Graduate Course 10.804, Chemical Engineering Department, MIT, May 4, 1982, Cambridge, Massachusetts USA.

100. Heising, C. D. 1982. Reactor safety and three mile island. , Department of Physics, Wellesley College, November 16, 1982, Wellesley, Massachusetts USA.

101. Heising, C. D. 1982. Reliability and risk assessment. , Graduate course in MIT Nuclear Engineering Department (22.312), May 6, 1982, MIT, Cambridge, Massachusetts USA.

102. Heising, C. D. 1982. The MIT research program in probabilistic risk assessment for nuclear power applications. , ILO Symposium on Systems Reliability and Risk Assessment, Massachusetts Institute of Technology (MIT), November 16, 1982, Cambridge, Massachusetts USA.

103. Heising, C. D. 1981. The reprocessing decision. , Q Division, Reactor Safety Division, Los Alamos National Laboratory, January 29, 1981, Los Alamos, New Mexico USA.

104. Heising, C. D. 1981. The supply of appropriate technology for the developing world. , 8th Annual WATTEC Energy Conference, February 18-20, 1981, Knoxville, Tennessee.

105. Heising, C. D. 1981. A comparative assessment of advanced reactor fuel cycles. , Engineering Physics Division and Health and Safety Research Division, Oak Ridge National Laboratory (ORNL), February 20, 1981, Oak Ridge, Tennessee USA.

106. Heising, C. D. 1981. Probabilistic risk assessment. , Nuclear Engineering Department, University of Massachusetts, April 29, 1981, Lowell, Massachusetts.

107. Heising, C. D. 1981. Engineering careers: nuclear engineering. , Cronkite Educational Building, Radcliffe College, June 30, 1981, Cambridge, Massachusetts USA.

108. Heising, C. D. 1981. Reactor accidents at pressurized water reactors. , Mitsubishi Electric Company Central Laboratory, June 19, 1981, Kobe, Japan.

109. Heising, C. D. 1981. A comparative assessment of advanced reactor fuel cycles. , Engineering Physics Division and Health and Safety Research Division, Oak Ridge National Laboratory (ORNL), February 20, 1981, Oak Ridge, Tennessee USA.

110. Heising, C. D. 1980. Analyzing the reprocessing decision. , Nuclear Engineering Department, MIT, May 15, 1980, Cambridge, Massachusetts USA.

111. Heising, C. D. 1980. Nuclear reactor and power production in developing countries. , Society of Women Engineers (SWE) national conference, June 25, 1980, Cherry Hill, New Jersey.

112. Heising, C. D. 1980. The MIT nuclear safety/reliability program. , Studsvik Nuclear Laboratory, October 27, 1980, Nykoping, Sweden.

113. Heising, C. D. 1980. Reactor safety research at MIT. , Sandia National Laboratory, Reactor Safety Division, December 5, 1980, Albuquerque, New Mexico USA.

114. Heising, C. D. 1980. Hydrogen production in reactor accidents. , Nuclear Engineering Department, Massachusetts Institute of Technology (MIT), October 1, 1980, Cambridge, Massachusetts USA.

115. Heising, C. D. 1978. The reprocessing decision: a study in policy-making under uncertainty. , Science Applications, Inc., July 1978, Palo Alto, California USA.

116. Heising, C. D. 1978. Analyzing the reprocessing decision. , Electric Power Research Institute (EPRI), August 29, 1978, Palo Alto, California USA.

117. Heising, C. D. 1978. Analyzing the reprocessing decision. , Operations Research Department, Stanford University, September, 1978, Stanford, California USA.

118. Heising, C. D. 1978. The reprocessing decision. , Nuclear Engineering Department, MIT, March, 1978, Cambridge, Massachusetts USA.

119. Heising, C. D. 1977. The decision to recycle plutonium: a study in policy-making under uncertainty. . Doctoral paper competition; paper won award., 1977 Western Regional Student Conference, American Nuclear Society (ANS), Doctoral Category, Oregon State University, March 23-26, 1977, Corvallis, Oregon USA.

120. Heising, C. D. 1976. Nuclear systems optimization. , Operations Research Department, Stanford University, June 1976, Palo Alto, California.

121. Heising, C. D. 1975. Short range infrared optical communication. , 1975 Region VI American Institute of Aeronautics and Astronautics (AIAA) Student Conference, Master's Category, Stanford University, May 1-2, 1975, Palo Alto, California USA.

122. Heising, C. D. 1974. Nitrogen dioxide and carbon monoxide levels in mission valley. , American Institute of Aeronautics and Astronautics (AIAA)

Student Conference, Bachelor's Category, School of Engineering, University of California, Irvine, May 2-4, 1974, Irvine, California USA.

123. Heising, C. D. 1973. Pollutants in san diego county. , National Science Foundation (NSF), Student Originated Studies (SOS) Program, December 1973, Arlington, Virginia USA.